ACTIVITY REPORT 1977

ACTIVITY REPORT

1977

by

E. DELANDE

W. DRENT

(Editors)

JULY 1D7S

TABLE OF CONTENTS

Foreword

I Administrative and Commercial totters

1 General Assembly

2 Board of Directors

3 Personae!

4 Convention with the Belgian Government

5 Negotiations with Gelsenberg AG

6 International Research and Development Progr

7 Research Contracts

8 Patents

9 External Fel*fi>ns

I I Safety Questions

1 Personnel

2 Radiation Protection

3 First Aid and Medical Care

4 Conventional Safety

5 Miscellaneous

I I I Safeguarding of Nucïear Material

IV Reprocessing Fiant and Related Services

1 General

2 In tervent ions

3 Fuel Reception and Storage Building

4 Water Treatment

5 Vent i la t ion

6 Management of Radioactive Wastes

6.1 Liquid Wastes

6.2 Bitutninization F a c i l i t y

6.3 Solid Wastes

7 l'r<Ktss O c t r o i labora tory

Intermediate Storage of Lo*-level Solid Wastes

1 Purpose 31

2 D e s c r i p t i o n 31

3 Equipment 32

4 Vent i l â t ion 32

5 S t a t - s of the Project 32

6 Layout of Building 23 33

VI General Services Department

i Personnel 35

2 Main Tasks 35

3 Work Orders 36

4 Breakdown of Time Spent 40

5 Consumption of U t i l i t i e s 42

VI I Industrial Development

1 S o l i d i f i c a t i o n and Conditioning of Liquid High-Level wastes

(LOTES process)

1.1 Chemical Flowsheet 43

1.2 Inact ive P i l o t - s c a l e Tes ts 44

1.3 Inv i t a t i on to Tender 47

1.4 I n t e r n a t i o n a l R & D programme 48

2 Treatment of Spent Solvent

(LUROWATT process) 48

3 Conditioning of High-level Non-combustible Solid Wastes

( Incorpora t ion in to POLYMER-CONCRETE) 49

4 Decontamination of HEWC Solut ions 49

5 Recovery of Uranium and Plutonium from Analyt ica l Aqueous Wastes 50

6 Treatment of Plutonium-bearing Solid Wastes

(ACID DIGESTION process) 50

VI I I Library and Documentation Services 53

IX Conferences and Symposia 55

Appendi*

t ijr"t- ht"v.i.' (Jt'ViTn in*; ilod i e s 57

FOREWORD

;.i;r,v:u'"-.i.: . tU ..;;r. •;•*..i:; i."-,r. p.tr.y ter l ii«ï Chetiicai Processing wl' I r radia ted Fuel», i s a jo int under-

: ;<•!;-.; T t ::I . 'M; . NôU-.-.r hrvrcy Agenoy >N£A).

l:.t L .r.;M:;y - j s ;.!3st : t'-iti-u ':y a i. onvention siîiou. in Pa r i s , ou Q^cvober -0» 19^7, and l t s Statute

a:;:ie.\cd th*L-r*u>, which ooth ::ar.e into farce on July 27, 193*», following r a t i f i c a t i o n of th* Convention

b> t:w 6iw;naï-Tw-s. 'ïtie Company, which has i t s seat at Hoi, Bvlgiur, is governed r e s w u a r i l y by the

Law ei til*.- ;ii\ui;>.'jrter:» S ta te .

Ti.r •'.•vvrnnt-nt* of the following twelve countr ies are nerahers of fcurochemic: Aus t r ia , Bel^ïuc, Qemark,

Fraact-, tae Federal Republic of Germany, I t a l y , Norway, Portugal, Spain, Sweden, Switzerland, and Turkey.

i:u or ig inal aims eî the Company were to carry out research and indus t r i a l a c t i v i t i e s connected with the

•/.ieir.ical processing of i r r ad ia ted fue l s , the use of products resu l t ing therefrom, arul to contribute to

t:it- t ra ining of s p e c i a l i s t s in these f i e l d s . The work* of the Company r e l a t i n g to these objectives have

j t tn described in the Activi ty Reports up to 1974.

in November, 1971, the Board of Directors decided to put an end tc the operation of the reprocessing plant

tovaris the diddle of 1^74, and to undertake 3 prograsne aimed at fu l fu l l ing Eurochectic's obligations

tv t rea t and sol idify -he radioact ive waste accumulated ons i t e . The reprocessing plant vas actual ly shut

d '*TI at the end of 1974.

la IV74, the General Assembly, with the approval of the Special Group of the OECD Steering Corsaittee for

N'iclnr Energy, decided to extend the dera t ion of the Company, o r ig ina l ly fixed at f i f teen years , for a

farther period of five yea i s , u n t i l July 27, 1979.

The a :arri of Directors adopted, in 1975, the tas ic technical programme and re la ted f inancial est imates

o/.'Hri^s a l l condit ioning, d^cor.taciinaticn, and storage operations corresponding to Eurocheque's legal

obligations to r,<e :a! t i l l e d during tht extension per iod. The Activi ty Reports for (973 and 1976 describe

t !''.• works ^.trrird oi..t -luring the f i r s t tvo years of that programme.

I-i. prt'M'ii: r-.p : : îvt.s the .il.itu.-i of th^se w^rks dt the end of 1977. This ynar has beer, uarked hy i;i-

t»ji.:,v i tâl >rui * f'c.inii'üi vîk -timed at t'l.iûrat ing a Convention between tururhernic and Che Belgian

L-ovfrnrT.fp.L u:i t .Vf ' / c r ol t he insta I Wit iu; " -* and execution cf the legal obi i gat ions o I t he Company • The

jr . i i i Convent i >;n was apt roved in prinripi t- by the Board of Directors and the tieneral Assembly in

if.-rera'r.i1:* t i 97 7.

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The basi • te-rmi.-al pr jgracse was continued .is planned, and the most s i gn i f i c an t works c a r r i e d out are

t h t f j 1 lowi - i^ :

Dt'CMitanination. of the p laat progressed s a t i s f a c t o r i l y , and the tenders by spec ia l ized firms tor

the in te rvent ion works planned for 1978 were eva lua ted;

The b i t u c î n i z a t i o n f a c i l i t y was successful ly t e s t ed v i t h low-level so lu t ions and the f i r s t campaign

ot t r e a t i n g mediuc-lev*! wastes was prepared;

The associa ted s torage f a c i l i t y was completed and the handling equipment ins ta l l ed and t e s t ed so

that s torage ca:i be&in in ear ly 197H;

Solutions O r the treatment and condit ioning of the l iquid h igh- l eve l wastes were evaluated both

from the technica l and economic point of view.

ADMINISTRATIVE AND COMMERCIAL MATTERS

I

I . : ' r j n ^ f t v -ji Smarts

At : : -• rvt-tiiij; . t ïiecer/cer 21 , ÏV77, the General Assembly approved, in accordance with A r t i c l e s b, and

i1.', I-.'-. . • t'. iî " iphf no . b of the S t a t u t e , the t ransfer of twenty-two shares held by the Société" Sa in t -

wv-în I ('tiL-a-Mousson to the Société Générale pour les Techniques Nouvelles (formerly Société Sa in t

e-bain ÎK- îini pa. s Nouvel les) .

1. i .omposition j f the Board of Directors

!hr General Assembly renewed the mandate ot the following D i r e c t o r s :

Mr. V. F r e r o t t e , represent ing the Government of the Kingdom of Belgium;

Mr. L. K. Maricq, represent ing the Société de Tract ion e t d * L l e c t n c i t é , and the Socié té E l e c t r o b e l ;

M: . i.. Hastrup-Birk , represent ing the Go\ eminent ot the Kingdom of oenmark;

Mr. I. A. N*jd, represent ing Aktiebula^tc Atomenergi, Stockholm, Sweden;

Mr. t. M. P i c t e t , represent ing the Government of the Swiss Confederation.

The General Assembly appointed the following Di rec to r s :

Mr. K. P. Randl, represent ing the Govern.T.ent of the Federal Republic of Germany, rep lac ing

Mr. *. iciir.idt-Ktister ;

>Yssrs V. r e r r o t and J . Lefèvre, represent ing the Co^jr.issariat à l 'Energie Atomique, France,

repl-K'ing Mr. B. Go ldschir,iut and Mr. R. Boussard r e s p e c t i v e l y ;

Mr . ::. (arr<-1 ra- i u : ; , represent ing the Junta de tnerg ia Nuclear , Portugal .

1 tu I-'! 1.)*.';;^ a l t e r r a t e s were appointed by the General Assembly:

--- Mi. K. rt.-sf.*rii, as a l t e r n a t e t.- Mr. F. P e r r o t ;

Mr. J. M.i'.'.-.t-i i e , as l i t e m . i t t to Mr, ..'. Lefevre.

/•.<- Gf.it': - il A-semöly r .ntwtd the ^.mdatc of Mr. V iatr.and (Belgium) as an a u d i t o r , in accordance with

Ai t ; ;. ;? ' lh: S t a t u t e .

; . 4 'fa r.d demerit Report, Balance Sheet, Profit and Luss Account

ir . i • r i • ; : • • v i t : \ r I i •• t e 1 ' • , .!nd , : a r i / , r . t o L , - v . 11 . i f t hi- .St a t u t o , t t i t ( ' V I N T a I A s . s e m b l y a p p r o v e d t h e

". i ;'..(»: •.•::* --.t !--•; - i t , a -, w. ! ! -i;- t i i r h-i ! .<•.. r s ' , . <-f ,in*i t h e i'r- t i t m<j i-i-s s Ac c o u n t t t>r f he t i r . a n c i a i y e a r

i ' ' ~ f , . : : - i i.•'.:•>: - -w ; ; - • ' : i .i t ••<. 'Vi-I i f >.,*; s ' ^ • • | l - r ! t , : ; ,u d i s c !>-• r g e d t h e i J i r e » E . i r ' - for t h e i r c o n d u c t o f

1. 1 £?*ction of CnaiiTnan and îce-chairmen

The Board e lec ted Mr. L. A. Ntfjd as Chairman,, and Messrs J . Lefivrc and R. P . RanrfL as Vice-chairmen

of the Board.

2. 2 Technical Conwittee

Ihe Technical Committee ne t three times in the course of 1977. Apart fro» reviewing the updated technical

pr^tr-imse re la ted to Eurochemic*s legal o b l i g a t i o n s and the re la ted a c t i v i t i e s of the Company, the Commit

t e e ' s ne t t i ngs were devoted e s s e n t i a l l y to the eva lua t ion of the technica l so lu t ions for the treatment

ana condit ioning of r.he h igh- level waste, and to advise the Board accordingly . For tha t purpose, the

I'ozr.i t t e t net once in Marcoule, France, to study the AVM v i t r i f i c a t i o n f a c i l i t y and to compare i t s tech

nical r x r i t s to thos* of the LÛTES and PAMELA proces ses .

3 PLRSOWitL

Cn January I , [977. the Company staff consis ted of Mb members. During the year under review, three per

sons h.ivt left the Company, while eighteen were engaged. Consequently, the Company s ta f f increased by

f i f t een , t o t a l l i n g I *>0 members AS of December M , 1977.

3. 1 Breakdown of Personnel by Na t iona l i t y , during 1976-77

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ADMINISTRATIVE

DEPARTMENT

13

CONVENTION WITH TnE BELGIAN GCVERWENT

F» 1 lowing ii ie B o a r d ' s a p p r o v a l , in December , 1976, of t h e g t n e r . i l l i n e s of a n a g r e e m e n t w i t h t h e B e l g i a n

Government r e l a t i n g t o t h e t a k e o v e r of t h e Company 's i n s t a l l a t i o n s a;id t h e d i s t r i b u t i o n be tween Belg ium

and Furoc heir, ic of t h e va r i ou s r e s p o n s it> i I i *: • e s re l a t e d t o t h e c o n d i t i on i n g , s t o r a g e , and d i s p o s a l of t h e

r a d i o a c t i v e w a s t e s , and d i s r a a n t 1 i n g et lb i n s t a l l a t i o n s , a N e g o t i a t i n g G r o u p , composed of r e p r e s e n t a t i v e s

of Be lg ium, Lu r o c hemic and NF.A, met on s e v e r a l o c c a s i o n s , i n 1977 , t o e l a b o r a t e a d r a f t C o n v e n t i o n on

t a k e o v e r of t h e i n s t a i l a t i o n s -ind e x e c u t i o n of t h e l e g a l o b l i g a t i o n s of t h e Company» k e e p i n g t h e Board

c u r r e n t l y informed on the p r o g r e s s ->i t h e m g o t i a t i o n s , In December , 1977 , t h e Hoard a n d t h e G e n e r a l

Asst.rir.hly app roved in p r i n c i p l e t h e d r a f t C o n v e n t i o n . The Board a l s o recommended t o t h e G e n e r a l Assembly

t o d é c i d e , in a c c o r d a n c e w i t o A r t i c l e s 1 0 , and la nf t h e S t a t u t e , a t h r e e - y e a r s e x t e n s i o n of t h e Company 's

d u r a t i o n u n t i l J u l y 27, 1982, c o r r e s p o n d i n g t o t h e p e r i o d r e q u i r e d f o r c o m p l e t i o n of t h e work t o be u n d e r

t a k e n by the Company i t se - i unde r t h e C o n v e n t i o n . The G e n e r a l A s s e m b l y ' s d e c i s i o n must be a p p r o v e d f n a n i -

rr,< ' i s i y by t he Spe,- i a I f.r.'up , p u r s u a n t t o Art. u "le I '• of t h e O . .vent ion on t h e Cons t i t u t i o n of Eur oc hemic .

She !,.*nve;it i'-:i p r o v i d e s t «>r t h e t r u r . s f e r <>i t h e i n s t a l l a t i o n s t o A B e l g i a n company t n b e c o n s t i t u t e d ,

r i t » r : . l t o .if. " th . - ;-,i *• • '.-imp m y " . For th*- p u r p o s e s of t r a n s f e r r i n g t h e o w n e r s h i p of F.urochemic ' s s i t e

and it- , i-ast-il \ ftt i" i is , t he upcr->tin«: l i c e n s e <»nd t h e c o r r e s p o n d i n g r e s p o n s i b i 111 i r s , a s we l l a s f o r

^•î lit. ..-iiCi";i:-,.iti,in and r ad i oa.' t i vr w a s t " r.ind i t i '<n i ng o p e r a t i o n s , t he s i t e i s d e v i d e d i n t o f c u r a r e a s ,

e t r a n s i t r w i l l be n i d t in s u c r c s s i v e s ' a g e s f i . e . a r e a by a r e a ) on t h e d a t e s and u n d : r t h e c o n d i t i o n s

i i ne J in th< '. > nv. r.f. i 'ii > ht a r e a s . . u p r i s i n g t h e r e p r o c e s s i n g p l a n t and r e l a t e d f a c i l i t i e s , a s we l l a s

t h e land er. wh i,- ;i IUV i n.*.'. ( i ! .it i ons t or t ; ' e t r e a tr ient .MU! s t o r ige ->l h i g h - l e v e 1 w a s t e a r e p l a n n e d t o be

• l i i i , - i i l be ï.r,i:ist .-r t e.' ; .ot l a t e r :_h.i;i h : !v 1, \'!,'). The a r e a s . u p r i s i n g t h e e x i s t i n g f a c i l i t i e s fn .

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::.* i r t I::L; :;: J;:-... >t.i.:\; ( „: i ,* i->act iv*.- wjstf . the research labora tory , the gv-aeral s e rv i ce s bui ld ings

f.iii rci.ti»'- :..,:: I ;t ;es w : I ; :•«. i r a n s i e r r e d in the course of 1961.

:.•; ret;.:'» : r the t r ans t* r oi ownership, the New uocpany will t,»kt- charge of the expenditure for d i s -

r '.j::t I i::fi the i:.s t.i I iat i,>u». a:id t o r th* conditioning» s t o r age , ami d i sposa l of the waste r e s u l t i n g frost

su>-h iisrumt I ir.g. Lu roc hen ic wi l l pay a lump sac con t r ibu t ion of *90 n i 11 ion Belgian francs û r the d i s

tan t li:iji expendi ture .

li.e Convention spec i f i e s the cleaning and decontamination operat ions to be ca r r i ed out by Eurocheque b e -

i.-re the t ransfer uf c e r t a i n a r e a s , as ve i l a» the works for which turochemic w i l l be respons ib le r e l a t i n g

t > the t reatment , condit ion ing, ana s torage of the l iquid and sol id wastes which r e su l t froat operat ion

; the reprovess ing plant and the cleaning and decontamination opera t ions .

HeârdinjC the h i 6 h- l eve l l iquid was te , i t had i n i t i a l l y been envisaged to use the LOTES process developed

by tur»Hrhexic, together with the PAMELA process developed by Celsenberg AC, Essen. However* in view of

the t irr.e schedule foreseen under the Convention for the t ransfer of the i n s t a l l a t i o n s , the Board f i n a l l y

-.«-lei't*-J the Affi process ir.sr.ead of trw* LOT E S process , the forser being technica l ly store advanced and

_.ipabie -'I' t r ea t i ng the wastes more r a p i d l y . The Convention therefore provides that the New Coopary wi l l

t a r r y . u t , on beha It ol Lurocheeic, a l l the works r e l a t i n g to the t r e a t o e n t , condi t ioning* and storage

•••i the high-levei l iquid waste from the reprocessing of highly enriched uranium fuel (KTR) » as well as

the cons t ruc t ion of the AVM i n s t a l l a t i o n , which can be used a l s o for the vaste r e s u l t i n g fro» the recoat-

r.issioned reprocessing p l an t . The h igh- level l iquid waste froc the reprocessing of na tu ra l and s l i g h t l y

e:iri-;:.ec urar.iuc fuel (Pl'REX) wi l l be t r e a t e d and conditioned according to the PAMELA process by Celsen-

her5 AG, in an i n s t a l l a t i o n erec ted by that cor.pany, on condit ions to be defined ir a separate agreesent

bet-een Kurochenic an-i uelser.berg {see bel.--w>.

•u^-iruing tee prj'rLer. .•: :lr.ar,cir.g a l l the expenditure r e s u l t i n g frctt the execution of fui Convention,

the Bcari has asked the. Special Crcup t e cake appropr ia te recomendat ions to the Gcvcrnoents p a r t i c i p a t i n g

ir. hur ochexic. In f a c t , zr-.e Belgian Gov^rrssent has asked that these Covernsents guarantee the financing

of r he expenditure required r\>r the proper execution <•! the Convention.

"%', WPh GCLSIMBLRG AG

B h i s t e ; ;. y r'..- ï ,\ S e c r r t . i r i * t , ii.ic s e v e r a l r o u n d s or n e g o t i a t i o n s w i t h t h e lier man Core-

I .. '.T.. \ •«! i ay. -m . i ^ r t - t T i m t , t he pur;, >se uf which would be to d r n m s t r a t e Ihe t e c h r i r a l

i : A^'i.iA j ' j . ' M ' S ' , -mi. :>• .-.--l i•! i I v .tb.'iit :- i x t y cub ic m e t r e s of f.urorheir.i<- ' s PUPtX w a s t e

i-.fi • 11 •.. T ; ";:'i,i : >. Vf. ; n s t e e f : ;ns M i i t J i i l e fo r l o n g - t e r m ; ' . T a m 1 . ^ c ' r t h i s p u r p o s e ,

it .;* is- •;;.>• 't ^ w i l l t o n ^ ' r u t , w i t n t he t inane i-u s u p p o r t ' t t h e Government of t h e F e d e -

'•rr„,iny, i p i i . - t i n s t a l l a t i o n TI r uro . h e ~ i . ' ' s s i l t ' . The a g r e e m e n t w i l l have t o be a p p r o v e d

.'<. rr.r > :.; ".;,.:-, r : : .e t * . r - s <t th*- (,(<iv.-nt i.-rs r . - ' t ' r r e r i r,-. above

, i ;:•*-?•' - i s ?•• . ; . / • . • • ' , . n <.•',. i' !i;i- I ••/.-. I i i t he f v\-"-•'.'*. : iifc t;it>1 met-".!

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c ipa t ing in Lurochemic, as well as a number of non-member organizat ions showed grea t i n t e r e s t in the

in te rna t iona l programme, considerable progess was made, i n 1977, towards conclusion of an agreement on

an in t e rna t iona l research and development programme on condi t ioning of n igh- leve l r a d i o a c t i v e waste .

However, as a consequence of the technical r e o r i e n t a t i o n of Eurochemic ' s high-K-,el waste programme in

the context of the Convention t o be concluded with tt -\ Belgian Government, and the dec is ion to l imi t

extension of Eur* chemie's dura t ion to th ree y- : r s , the Board of Direc tors agreed to postpone the i n t e r

na t iona l programme and to reconsider i t in a d i f f e r en t c o n t e x t , following eva lua t io r of the prospects

for in te rna t iona l research and development opera t ion at Mol.

7 RESEARCH CONTRACTS

7. 1 Contract with Gelsenberg AG

Collaboration with Gelsenberg AG continued during 1977 under the terms of the research con t rac t concluded

in 1975. It i s the purpose of t h i s con t rac t to develop and t e s t a process for the manufacturing of .i

product composed of phosphate g lass beads incorporated i n t o a metal matr ix , and su i t ab l e for the long-term

storage of Eurochemic's PUREX waste . As add i t iona l f inanc ia l support is expected to be made avai lab le by

the Federal Ministry for Research and Technology, the dur tion of the cont rac t w i l l be extended for another

two oi three years , u n t i l 1979, or 1980.

7 . 2 Wet Combustion

Negotiations were s t a r t ed with the Kernforschungszentrum Karlsruhe (KfK) with a view of concluding a"

agreement on wet combustion of sol id was tes . L'nder t h i s agreement, Eurochemic and KfK would col labora te

for the pu-pose of developing, a t KfK's charge , a laboratory i n s t a l l a t i o n capable of t r e a t i n g Eurochemi^'s

combustible plutonium-bearing sol id wastes , and of car ry ing out research and development work on the

r e c t o r y of plutonium from the combustion re s idues ,

fa °ATENTS

ts. 1 Eurowatt Process

In the year 1973, patent app l i ca t ions were f i l ^d L. the Federal Republic of Germany, in Japan, in the

United Kingdom, and in the United i . a t e s of Americ. jr a "Process for the Treatment of Organic Wast*

(Known as the tURQWATT Process )" , correspondir. , t. ne patent granted in Belgium, on September 30, 1974,

und'- patent number 819 S18.

The patent was granted by the United S ta tes of America for the term of seventeen yea r s , as from

August .1, 1977, under the patent number '* ,039,468,

'Iht- patent app 1 i t at ion in t he Fédéra 1 Kepuu 1 ie f'l' Germany , H led on September 10, 1973, under number

I' r> 40 J I ! . ' J , w.j s laid open t<' the public in the form of .in "of fen legungssd i r i f t " , on March 25, 1976,

Further examination of tr,.. ; ap;il K al i i.n r equ i res a novelty .start.'h and the prosecution on the pa ten t

a b i l i t y .;i tin invention, prior to September 10, 1982.

Fatent app l i ca t ions were f i l ed in

Grtat B r i t a i n , on September ! , 1975,

under number 37,462, and in Japan,

on September 12, 1975, under number

111575/75.

Various o f f i c i a l ac t ions from the

B r i t i s h Tate.it Office were t rea ted

during 1977.

In Japan, a novelty search was r e

quested, and f i l e d at the Patent

Office, on March 3 , 1977.

t'tû' en (he OiAtattaticn c$ thz

8. 2 Embedding of Solid or So l id i f ied HLW into Metal Matrices

In Jai.uary, 1977, Eurochemic received from the Patent Office of Great B r i t a in the Deed of Le t te r s g r a n t

ed under number 1,446,016 for s ix t een years , as from July 22, 1974, for the "Method for the Condit ioning

of High-level Radioactive Wastes for the i r Safe Storage and Disposal" .

A patent extension j o i n t l y f i l ed by fcAiroche&iic and the Gelsenberg Company, on November 15, 1975, under

the number P 25 51 349.9, was ' a id open to the public in an "Offenlegungsschrif t" , rm May 26, 1977.

8. 3 Incorporation of Radioactive Solid Wastes in Polymer-concrete Material

A provis iona l app l i ca t ion was f i led in Great Br i t a in , on March 2 1 , 1977, under the number 11,849. The

complete spec i f i ca t ion wi l l be submitted at the beginning of March, 1978.

9 External Relations

As in previous years , staff members of Furochcmic pa r t i c ipa t ed in several symposia, panel meetings,

congresses, e t c . . (see Chapter IX). The Company continued i t s cooperat ion with and a s s i s t a n c e to i n t e r

nat ional organizat ions and foreign i n s t i t u t e s working in Che nuclear f i e l d .

iurochemic welcomed many v i s i t o r s , e x p e r t s , and s tudents from member and non-member c o u n t r i e s , who want"

cd tu hi. informed on reprocess ing , decommissioning of the reprocessing p l a n t , and waste management. Most

of them a t so wanted to exchange ideas aid opinions on the i r spec i f ic problems with Lurochemic ' s staf f .

Speri.il rient i;Ti siiuuld be m.nie of the large number of Japanese v i s i t o r s , who were sent to Europe by the

Japan At oïric Kttergy i nimi ss i un, var ion.s Japanse un i ver si t i es , and pr i va te i ndust r y .

http://Tate.it

http://Speri.il

A Urge number of requests for information and documentation (see Chapter VIII) was dealt v i t h . More

over, the Company's external re lat ions service handed out many photographs and s l i d e s on Eurocheaic's

operations and on reprocessing in general, whenever they were asked for . Three f i l a s shot during the

construction and startup of Eurochemic's ins ta l la t ions have been lent to schools and research i n s t i t u t e s ,

on several occasions*

The most important v i s i t o r s in the course of 1977 were the fol lowing:

In Jlarçh :

— Hr. C. C. Chapman of the Bat t e l l e Pacific Northwest Laboratories, Richland, Washington, USA.

— A group of professors and students of the Université de L i ige .

Is.ïteï:

— A group of experts from the German Kernforschunvszentrum Karlsruhe, who wanted to discuss problem

in the f i e l d of waste storage and disposal .

— A delegation of the European Parliament, headed by Hr. Flâmig, in viev of discussing problems

related to waste management.

Members of the Commission of the European Communities and of the Customs Cooperation Council.

In_June:

— Members of the City Councils and of the Civil Defense from the Dutch province of Limburg.

In_August:

— A delegation from Che Turkish Atomic Energy Commission was more particularly interested in having

a look at the treatment of medium-level waste and the Development Department.

Members of the Advisory Committee of the NV Gemeenschappelijke Kernenergiecentrale Nederland (the

Dutch Joint Nuclear Power Station Ltd).

Members of the Korean Atomic Energy Research Institute.

— A grouo of journalists, whose visit was part of an Information Day on the Nuclear Industry in

Belg,Um, organized by the Belgian Nuclear Forum.

Eurnchemk g»ve every assistance Co the preparation of a film by the German Geaellschaft fur Wiederauf-

arbeitung von Kernbrennstoffen mbH (Company for the Reprocessing of Nuclear Fuels Ltd), Haimover, on the

reprocessing of irradiated fuels, the conditioning and storage of radioactive waste.

SAFETY QUESTIONS

*

1 PERSONNEL

Dur int 1977. as was already the case in 1976. the Health and Safety Dépannent staff consisted of twenty-two workers, including two university graduates.

2 MOIATIM rHOTECTION

Staff umbers of the Health and Safety Department spent swat of their tine fulfilling the duties of the physical control in a Class 1 nuclear facil ity, as determined in Article 23. I of the Belgian Royal Decree of February 2. 19*8.

2. 1 Person**! Monitoring

— Individual External Dosinetry —

Routine neasureaents baad on pen, thermoluminescent and filabadg* dosinvters were continued in the sane way as mentioned in the previous annual reports.

995Ê.I9.M .W9ti.?9Qï

The allowed weekly dose équivalent is 230 nilliren; the quarterly dose nay not exceed three rea, and at the end of each year the accumulated l i fe dose nay not exceed MS-U) rem, in which S stands for the years of age of tb* person concerned.

Any excess of the allowed weekly dose of 230 aillires) must be authorised in advance by the issuance of a Planned Radiation Exposure Permit (PREP). During 1977, a total of thirteen PREP's were issued, all of then for a weekly dose of SOO ail l irea or less.

The quarterly aaxiaun permissible dose equivalent of three rea was slightly exceeded in one case, when 3.01 rea was recorded. The maximum permissible accumulated life dose of 5(N-I8) ren was not reached by any worker.

The following table shows the breakdown of Eurocheaic's workers according to the whole-body external irradiation dose equivalent recorded for the year 1977.

DEPARTMENT

POD

GSO

IOD

MSO

Others

TOTAL

<_ 500

mrern

20

76

21

10

1

80

501-

1,000

mrem

2D

5

3

3

0

31

1 ,001-

3,000

mrm

14

4

1

9

0

28

3 , 0 0 1 -

5,000

mrem

14

0

0

n

0

11

f_ 5,000

mrern

0

0

0

0

i;

Ç

10

The highest yearly dose equivalent recorded was 4.82 rem.

The tota l dose recorded for tr< whole of the Company staff amounted to 153.9 man-rea for the year undv-r

review; the total dose to outside personnel (hired prov i s iona l ly , or trainees) amounted to 20.7 man-rem

for the year 1977.

ugSE_TC_THE_f:XTKEHIXIES

When workers are exposed to the risk of s ignif icant doses to the e x t r e s i t i e s , usually the hands, lichium-

fluoride d isc dosimeters are handed out . In a l l , 821 L i F - d i s s were issued during 1977. These dosimeters

•re read at the Dosimetry Department of the CEN/SCK on a monthly bas i s , or immediately in .ase of a

suspected high dose.

Neither the quarterly maximum permissible dose of 15 r e s , nor the yearly maximum permissible dose of 60 r

were reached by any worker. The highest yearly dose recorded was IS.89 rem.

üOSE_TO_TrlE_SKIN

In order to calculate the total external irradiation dose to the skin, the B-doses ceajured with the film

dosimeters are added to the external whole-body irradiat ion doses .

Neither Che quarterly maximum permissibl. dose to the skin of eight rem, nor the yearly maximum permis

s ib le dose of th irty rem were reached by any worker. The highest yearly dose recorded was eight rem.

The assessment of an intake of radioactive material i s based on the analys i s and measurement of b io log i

cal samples. In case of doubt, or of pos i t ive r e s u l t s , additional information can be obtained from whole-

body counting or lung counting, both of which are performed at the CEN/SCK.

A pluconium-wound counter was kept ready for use. During 1977, one wound counting was carried out; no

contamination was detected.

During 1977, a total of 1,003 urine

samples, co l lected as a routine, or

after incidents , or after a sus

pected intake, were analyzed in the

bio-assay laboratory; 535 urine

samples were analyzed for plutonium

a-act iv icy (381 routine, ind 154

special or urgent); 396 samples

werj analyzed for total ^-act ivity

by the oxalate method (325 routine

and 71 special or urgent); 72

samples were analyzed for uranium.

I t

Ie tour .tev cases» the a -ac t iv i ty of the urine samples analyzed for plutonium exceeded the inves t igat ion

level (Ü.2 pCi for a 24 h sanple) . After subsequent sampling and measuring, the a c t i v i t y remained above

the reference level for a-plutonium in one case; t h i s was further examined. Lung counting and determi-

nation of the isotopic composition of the plutonium mixture revealed that the body burden vas ve i l below

the permissible l e v e l .

In the f ive known cases of internal plutonium contamination, the internal dose to the bon* vas evaluated

by means of the La fuma method, taking into account the amer ic ium-241 growth from the plutoniiaa-241. Two

of the workers concerned are not allowed to work in places with a plutonium-inhalation hasard (cf Act i

v i t y Report 1971); the other three are instructed to limit exposure to any plutoniui- inhalat ion hazard.

All urine analyses for to ta l ^-act iv i ty showed re su l t s below the invest igat ion level for strontium-90.

The resu l t s of the urine analyses for uranium were a l so below the invest igation l e v e l .

During the year under review, Eurochemic participated in an international comparative experiment on plu

tonium determination in urine, which was organized by the German Kernforschungszentrum Karlsruhe. Our

laboratory obtained the best r e s u l t s .

2. 2 Plant Monitoring

The task assigned to the radiation protection group in the plant includes frequent contamination and ra

diat ion surveys, ass is tance during hazardous operations, routine control of compliance with safety pro

cedures, and advising on the execution of most interventions.

During 1977, a to ta l amount of 793 Hazard Work Permits were approved after invest igat ion .

Rinsing and decontamination of the plant equipment was continued •'•> order to further reduce irradiat ion

and/or contamination hazards during the projected interventions.

In the Fuel Reception and Storage Building, segregation of solid waste was continued. The low-level

sol id wastes were conditioned in view of being transferred to the Waste Treatment Fac i l i ty of the CEN/

SCK.

Solid wastes with a higher ac t iv i ty level were cut up and packed into baskets in view of storage in the

Solid Waste Pond, after the la t ter wi l l have been emptied and cleaned. Debris of undissolved fuel pins

were likewise packed in leak-tight boxes in view of storage in the Solid Waste Pond.

SENA fuel elements were prepared for shipment to France.

Due to the buildup cf active dust , the MDE and HUE (medium depression exhaust, high depression exhaust)

f i l t e r s and p r e - f i l t e r s of the vent i lat ion building had to be replaced.

In the associated plant f a c i l i t i e s , a special effort was made to improve the overall safety by e l i m i

nating the stored wastes as much as poss ib le , by cleaning up and decontaminating the various c e l l s and

rooms in which small incidents had occurred en equipment had developed leaks.

Special attention was given to the various safety related aspects of the projected act ive operation of

the Bituminization and Eurostorage F a c i l i t i e s (Buildings 26 and 27) , more particularly in view of accept

ance by the approver body, CORAPKO.

1Z

2. 3 Hon iter ing of Uboretories

In addition to frequent survey* (or*radiation and contaminâtion, and controlling of coamliance with safety procedures, special care was given to the general decentanination of the glove keaes and the analytical eeuipmtnt in the Analytical Laboratory.

Partly cold and partly hot develop wint work on the conditioning of medium- and high-level wastes was continued in the Research Laboratory. The general clean-up of none active arena in the lenearch Laboratory, including the dioaantHng, conditioning and disposal of several glow boxes, son* of which were contaminated with plntoniwaraaide powder. was carried oat onder surveillance.

#

2. 4 Monitoring of Transports

Transport vehicles leaving the s i te were checked for compliance with the IAEA transport regulations.

2. S rtonitorina of Stack Releases

During 1977, no fuel was dissolved. Consequently, no release* of krypton-SS, iodine-131, or tritiun occurred through the stack. The releases of o and 6 particulate activities were kept far below the allowed levels.

2. 6 Are* Monitoring

Thermoluninescent dosimeter* were used to make routine meaaureaent* at sixteen different locations on and off the site ground, to detect possible radiation levels above natural background. Ko abnormal readouts have been recorded.

Environ»-atal water was sampled and measured for total a and total S activity; the activity measured in the 101 samples which were collected was never higher than normal. Monthly, rainwater samples were taken at five locations (three on and two off the s i t e grounds), sad measured for soluble and insoluble total a and total S activity; all measurements were within the normal ranges.

The Dessel air-monitoring station, downwind from the stack, did not register any activity above the normal natural or fall-out activit ies .

2. 7 Assessment of Projects

In a l l , eleven Internal Project Applications were approved aft«r investigation by the Health and Safety

Department.

2. 8 Regulatory Control

Peroanent regulatory control of compliance with regulations and safety procedure* was carried out by the approved body, COftAPRO, by mean* of twenty-four inspection» of the faci l i t ies and the requested a posteriori approval of two important lnternsl Project Applications.

13

j FIRST AIü AND MEDICAL CARE

During 1977, f i r s t aid and medical services were rendered as in previous years . According to regulat ions ,

371 preventive aedical examinations vere carried out . Heart examination by means of an e lectrocardio

gram, and the determination of cholesterol content in the blood of s taf f member» over forty were cont i

nued. During 1977, eighty-three examinations have been performed.

Thirty-four workers were vaccinated against influenza.

A refresher course was given tc the f i r s t -a id personnel.

4 CONVENTIONAL SAFETY

4 . 1 Accidents

In a l l . ten non-radiation accidents occurred on the s i t e . This makes for an accident frequency of 33.5

per mill ion working hours for 1977. In 1976, the frequency vas 30.3; in 1975. i t was 19 .5 . Mo permanent

inval idi ty resulted from any of the cases . Temporary absence from work due to these accidents amounted

to 231 days in 1977. In 1976 i t t o ta l l ed 162 days; in I»75, 221 days.

4. 2 Fire-f ight ing Equipaient

All f i re - f ight ing equipment was regularly checked; routine maintenance was carried out. Routine t e s t s

of the engine of tl.e f i re - f ight ing t r a i l e r pump were performed.

The foam-injection system used as a second f ire- f ight ing means in the drum-fill ing s ta t ion and the drum-

transfer room of the bituminisation unit (3 . 26) was compl ied . Prior to being i n s t a l l e d , the equipment

was tested under simulated condit ions; the results were good.

The s ignal izat iun of the f i r e - f i g h t i n g hydrants on the s i t e and around the Eurocheaic residence tower

was improved. S

The f ire - f ight ing equipment for Buildings 23 and 27 was purchased,

4. 3 Regulatory Controls

Regulatory inspections of e l e c t r i c a l in s ta l l a t ions , l i f t i n g devices , compressed-fluid systems, and safety

be l t s were performed by AIB inspectors. Fire-fighting and f ire-detect ion equipment, alarm systems, e l e c t r i

ca l , gas and heating ins ta l la t ions were controlled regularly, following regulation*. Furthermore, ind iv i

dual protective equipment, areas for the storage of inflammable l iquids , ladders, cotnpresscd-gas b o t t l e s ,

l i t e . . . wtxt! r e g u l a r l y c h e c k e d .

4. 4 Protective Equipment

The existing protective equipment was maintained and the apparatus for leak-tightness t e s t ing of gas

casks used on a regular b a s i s . Air-supplied intervention equipment has been kept available for in ter

vent ions .

5 MISCELLANEOUS

5. 1 Instrumentation

The portable and fixed conitoring instruments required regular maintenance and repair. Reca libra t i ens

were made, using various act ive sources. Burst detectors and ambient y-radiation monitors were tested

regularly .

New fixed and portable monitors have been purchased for the bituminization and storage f a c i l i t i e s , and

for replacing obsolete equipment in other un i t s .

S. 2 Emergency Preparedness

An emergency stock of equipment i s kept in a store room near the main entrance to the s i t e , avay from

the active areas.

the d iese l generators are tested monthly. Cuts in the pover supply were simulated in order to test the

emergency procedures.

The radiotelephone communications system with the CEN/SCK and the Civi l Defense Headquarters has a l s o

been tested each month.

5. 3 Secur i ty

The guard room is continuously occupied. The good condition of the fence around the site is checked

daily. Routine meetings with the representatives of the various nuclear establishments in the Hoi area

are being held; the CEN/SCK is acting a» a coordinator in this connection.

5. 4 Safety and Health Committee

According to Belgian regulations, a Committee for Safety, Health, and Embellishment of the Place of

Work, chaired by the manager, and consisting of twelve effective members, six of them being designated

by the Management, and six being elected by the workers, net nine times, during 1977. The Safety and

Health Committee regularly designates some of its members for inspections of the various work areas.

SAFEGUARDING OF NUCLEAR MATERIALS

15

During 1977, internal control in the f i e l d of safeguards wa* restricted to surveying and recording

only one shipment of two plutonium-oxide containers and a few transfer* of nuclear material contain

ing wastes.

At the end of 1977, the statement of the cumulative material unaccounted for (HDF) read • • follows:

" - ^ M J C L E A R MATERIAL

HUF - «^___^

Cumula t ive MUF at t h e end of 19rs

Nuclear m a t e r i a l c o l l e c t e d in

wastes d u r i n g 1977

Cumula t i ve rtUF at t h e end of 1977

C u r s j l a t i v a MUF In \ o f ou tpu t

LEU (kg)

403.3

58.2

345.1

0.19

Pu (Kg)

10.708

2.479

8.22R

1.21

HEU (Kg)

6.933

0

6.933

0 .51

REPROCESSING PLANT

17

1 GERERAI

With A crcv of t i v , working ia A f i v e - s h i f t schedule, th* plane va* kept in standby dur in» the year

under review. Ibt remaining plaat personnel worked on the bituainixation program*.

Work i a toe plaat vas devoted mainly to the fo l loving operation*:

— - Local chemical rinsing with such reagents as H SO ; SAO ; H30.; J i t e r ; ftadiac '-ash; e t c . . .

- ~ Loc-t decontaBination with high-pressure water-spray pump (Snec J e t ) .

-— Mechanical cut ting-up of obsolete equipment and highly radioactive piping.

2 INTERVENTIONS

A summary overview of the in t e rven t ion work executed in the c e l l s is given be lov .

Ce l l IA/IB was decontaminated and cleaned up.

The jacket of the t h i r d d i sso lver (2216-1) in ""-ell 02 sprung a leak during a loâl chemical r i n s ing

with H-SO,. A second leak was detected on the cooling j acke t of the f i r s t i i s s o l v e r ( 2 2 . - 1 ) ; the th i rd

d i s s o l v e r was sh ie lded .

Letks a t the e l ec t rodes of the off-gas scrubbing columns 222-3, 222-*,, and 222-5 in Ce l l OS were r e p a i r

ed.

J e t s 22IJ405 and 22IJ406 in Cel l 06 were cut and unplugged; vessel 223-6A/B was decontaminated by h igh-

pressure water-spray pump (Smet J e t ) , lowering the r a d i a t i o n level from 40 R/h t o < 100 s* /h . The same

procedure showed no r e s u l t s on vessel 231-11, because i t i s d i f f i c u l t to get a t .

A f i r s t , rough cleaning of Cell 13 was car r ied ou t .

A sanpling of Raschig r ings was ca r r i ed out in vesse l s 231-71 and 232-41 in Cell 14 by removing the

Raschig r ing sampling device . The scaffolding necessary for the complete removal of t h e Raschig r ings

from the tanks was se t up.

A sampling of Raschig r ings was ca r r i ed out in vesse l s 251-8A/E in Cel l 17, ami the scaffolding for the

complete removal of the Raschig r ings from the tanks was se t up.

A q u a l i t y control of the in te rcyc le evaporators 231-/ and 232-4 in Cell 20 was c a r r i e d ou t ; no cor ros ion

was de tec ted , the mater ia l th ickness being between 3.9 and 4 tun.

Rework tank 252-12 in Cell 21 was decontaminated by Smet l e t ; the rad ia t ion level was lowered f rem an

average IS R/h to one spot of 1.5 R/h. K<fuipment for the removal of ionêxchange r e s i n s was i n s t a l l e d ;

the r e s i n of the ion-exchange columns 24M-5A/B/C and 2365-5 was removed and gathered in 30 I waste

box*». The %p-bottling box and the Np-tnetering wheel i2J6j~i ) were dismantled.

The decontamination of phase separator 252-25 in Ceil 23 was s t a r t e d .

Box II w«?s removed from Cell 31 in view oi bt-ing dismantled.

The HÏX fhi«hly enriched ur-miutî.j ho t t l t ng svstrir, in C*II 34/3* wis à i sra-mt U"i.

All contaminated equipment w,is removed from Zone 10.

Zone 29 was decontaminated and

painted again.

Contaminated concrete va» re

moved from Cell 8604.

Ove/ivia» on the decontamination

ca t'.i. two-itoiage bo*eJ jet

love- lev ei iamplei in loom J 54

ci BaUding } .

Qecontaminatinn e 5 loui-teveJL

iampte itonagt box, a$teA tlie

box mindou hot been lemoned.

Tkeie opvuUioM M.H- cavUed

cot in yiMtic tent, uUth juW

Protection.

I»

FUEL RECEPTION AND STORAGE BUILDING

3. 1 Personnel

Work in the Fuel Reception and Storage Building wak actually carried out by «is shift workers (crew* of two, working in a three-shift schedule), and four daytin* workers, including supervision. Work was mainly devoted to the handling of fuel elements, and the treatment of solid wastes.

3. 2 Hindi ing of fuel Elements

The following fuel elements were s t i l l in storage at the end of the years

1,077 NPD/DP elements (» 14.4 t of depleted uranium)

54 PAT elements ( « I I kg of H X enriched uranium)

6 EL-4 elements (" 37,6 kg of I.IX enriched uranium)

2 SENA elements (• MO kg of initially 3.31 enriched uranium)

Twenty-eight fuel pins of the two SEHA elements were packed separately into a closed bo», in view of

separate nhipment.

The two SENA elements were repacked for transport; heads were installed, and the elements packed into transport boxes. Shipment to France was scheduled for January, 1978.

At Chi end of the year, possibilities for the removal of the fuel elements from the Storage Pond were

being investigated.

3. 3 Treatment of Solid testes

The following waste treatment policy has been adopted:

Waste suspected to contain f i s s i l e material (tt/Pu) will be stored into tight stainless-stael

baskets.

Highly radioactive waste (material from structural éléments; will be stored into closed

stainless-steel baskets.

Both tight and closed baskets will subsequently b* stored in the Solid Waste Pond.

Low-level radioactive waste (< I R/h) will be treated and conditioned in view of dispossl into the sea.

It is expected that 54 tight and 110 closed baskets will be necessary. When emptied, the Solid Waste

Pond will be decontaminated, cleaned up, and engineered for the final storage of these waste baskets.

20

—-- Solid Vaste froc the Storage focd —

All Iou-level vaste vas removed from the Storage Fond (SP):

37 LE17KEL racks;

10 storage boxes;

330 LEL/KEU storage and transport boxas;

I fuel-loading feeding dev ice .

These wastes were a l l cut up and put into 220 vaste drums of ZOO 1; the vaste drums vera transferred to

the Waste Treatment Department of SLLGONL'CLEAIRE for subséquent condit ioning.

The s ixty activated s t a i n l e s s - s t e e l p la tes from Dodevaard vere cut up and packed into closed baskets .

Packing of highly adioactive waste into closed baskets was s tar ted . At the end of the year, ten baskets

had been f i l l e d vith end-pieces , springs and spacers of fuel elements.

Sixteen OTTO IIAHK elements were dismantled by cutt ing off the thirty-two end-pieces and taking out the

220 t i e rods. The cutting-up of the end-pieces with the mechanical saw vas s tarted. However, at the end

of the year, the mechanical saw was under repair: i t s driving wheel and s l id ing bridge were damaged.

Consequently, the material which has to be cut up has been provis ional ly f ixed .

§2i iË_^ste_f rom_tê_Solid^W«u_Pond

All fragments of rods suspected to contain either uranium or plutonium vere segregated and packed into

tight baskets, which were subsequently transferred to the Mechanical Treatment Pond (MTP).

All high-level solid waste was equa.iy transferred to the Mechanical Treatment Pond.

Tue Solid Waste Pond was dusted by means of a vacuum cleaning system; the water was removed. Radiation and

contat>.:nation checks of the SUP revealed radiation l eve l s of up to 0.05 R/h and contamination leve l s on

wipe t e s t s of up Co 850 tnR _ at the surface of the s t ee l l in ing of the tank. The SUP was covered v i th a

c l a s t i c roof and is awaiting f inal decontamination.

— laÊi.tsââiss-iÊsil-22) —

The obsolete closing system of the dissolver l id s in Cell 03 va» dismantled. Part of the ce i l ing of the

.e l l pit was cut away, and t e s t s are being conducted to find the best method for removing waste from the p i t .

!)eçoptaminatior_Sho2s_iRoomj_]041_|05 i_207) -—

Tue heavily contaminated floor oi Room 104 was dug out; the resul t ing waste was conditioned. The drain

lines cowards the interfiled i ; i te-Uvel waste (ILW) tanks were rearranged in order to bypass the sand separator.

. -iew ci licce[c fioor and d> tin gutter were bui l t ; obsolete equipment was cut away (sand separator, cask-

cuulinK tank, s t a i r , e t c . . . ) . Decontamination of obsolete equipment was carried out, partly by means of

clien; it.i Is, p.irtly liy me.iiis of tl.- high-pressure water--spray pump (Smet J e t ) , In addition, about 380 cad

mium iH!itr(,'n-.'ibsurpt i pl.iU'S were de. oncaninated.

21

4 kATER TREATMENT

While work was going on in the Solid Waste Pond, one of the purification loops vas used to treat the

-.iter of this pond. Quite sow dust was collected or the Mechanical filter, and «as reaoved, together

w:th the pr«coating layer into the silo waste tanks for the collection of solid slurries froa the

«aler treatment.

Tue second purification loop va& alternately used for the treatment of the water of the Storage Pond,

the Mechanical Treatment Pond, and ;be Reception Pood.

Segregation and transfer of wastes often resulted in considerable water pollution. Backwaahiog of the

mechauical filters of both purification loops was frequently necessary (about once a week); regeneration

of the cation exchange bed and the mixed bed was required once or twice a month.

5 VENTILATION

As from November : , !°77, the vent i la t ion crew was reinforced by an operator froa the Waste Treatment

Group. At the end of the year, the crew consisted of two operators and one supervisor.

The main operations carried out by the vent i lat ion crew during the year under review can be summarized

as fol lows:

In Building 4 heating elements of PS I (primary supply), and PS 2, and a annual valve of the exhaust

duct of the high-depression vent i la t ion c i rcu i t (KDE) were repaired. In order to prevent contamination

of the dry-pack f i l t e r s , a p r e - f i l t e r was instal led in the recycling duct from Corridor C 6.01 to

D 6.01. The non-return vslve of fan 284-4B and the flow indicators of the recooling c i r c u i t s I , I I , and

III have been repaired. Connections have been made for Di-octyl -phtalate (DOP) introduction.

In building 5 two s ta in l e sa - s t ee l f i l t e r casings for the o f f -gas c i rcu i t have been s e t up; the f i l t e r

housing» and the non-return valve of fan 584-5 have been repaired.

In Building 8 the PVC duct in the ves se l -vent i l a t ion c ircui t haa been repaired. In order to ensure a

good vent i la t ion of the fume-hoods and boxes i n Room 216, now serving as an analyt ical laboratory for

Building 26, appropriate modifications and adaptions have been made.

tn Building 24 the non-return valve of fan H 197 has been repaired.

In addition to general maintenance work, and the above mentioned repairs , a great deal of work has been

devoted to the followup of the v e n t i l a t i o n - i n s t a l l a t i o n t e s t s in Buildings 26 and 27, carried out by the

supplier. These t e s t s were almost finished by the end of 1977.

As an information, Che following table summarizes the consumption of p r e - f i l t e r s and absolute f i l t e r s in

the various vent i lat ion c i rcu i t s during the last s ix years.

22

«•Mints of Filttrs Use* in the Vtntflatio* Circuits «nring tht Tiers 1972-77

V e n t i l a t i o n C i r c u i t

Labora tor ia * -

Hood Ex t rac t ion

Laborator ia» -

Room tu tpac t ion

Reception Bu i ld ing

- Ex t rac t ion

P lant Bui ld ing -

HOE

HOE

Rooms B. S

Rooms P. 21

Rooms B. 8

Off -gas B. 5

Tanks B. 1 -

Vassal V s n t l l a t l o n 1

Vssaal V e n t i l a t i o n 2

Off -gas B. 8

i Ca l l 03

Typa of F i l t a r

p r a - f l l t a r

absolut» f l l t a r

p r a - f l l t a r

absolute f l l t a r

p r a - f l l t a r

abso lu t * f i l t e r

p r e - f i l t a r

absolute f i l t e r

p r e - f l l t e r



p r e - f l l t e r

absolute f l l t a r


absolute a i r

f i l t e r ( M F )

M F

m

p r e - f l l , . e r


p r e - f l i t e r

absolute f i l t a r

1972

1?

2

6

16

44

44

eo 1

8

15

4

4

4

30

6

12

132

1

S

1

1

1973

15

-

20

20

44

-

84

sa

24

8

6

4

4

20

-

36

116

4

4

1

1

Year

1974

15

16

--

sa -

4

-

12

16

6

4

4

20

2

8

164

5

5

2

2

1375

17

-

20

-

-44

28

-

24

-

2

4

4

6

4

-88

1

1

1

1

1976

--

--

44

-

25

-

56

24

6

4

4

6

2

-36

•\

2

1

1

1977

15

-

20

-

58

4 *

85

60

28

24

4

2

-

6

2

-40

1

1

-1

23

6 HANAGLMEOT OF RADIOACTIVE HASTES

6. 1 Liquid testes

The following table g ives an overview of the production of l iquid wastes during the year under review.

(teterUl Balance for 1977

Type of Waste

Condensate Waste

Col ' ' teste

Wartr. Waste

Hot Waste

Hot Condensate Waste

Upper A c t i v i t y L i m i t t C i / m 3 )

a

Lia"7

1 . 1 0 - 6

1 . 1 0 ' 3

6

1 . 1 0 - 6

-4 1.10

3 . 1 0 - 2

100

104

Volume (m )

18.750

6.353

3,610

1,230

27.5

The whole of condensate, cold and warn wastes has been transferred to Che Waste Treatment Unit of the

CEN/SCK. Before being transferred, however, the cold and warn wastes had been neutralized with haOH.

All hot wastes tuv? been concentrated in the Nuclear Cherical Plant (NCF) Evaporator, ac an average 3

evaporation rate of 1.3 m /h .

Because of an accumulation of so l ids in the intermediate low-level vaste-scorage ve s se l s !<*'.-5 and 266-6,

and in the transfer l i n e s , d i f f i c u l t i e s have bee' encountered in transferring hot waste frost Building I

(unit 266) to Che low-level waste building (no. 8 ) .

i 3

The hot waste concentrate (27.5 n ) resul t ing from the concentration of the hot waste (1,230 m ) , has

been transferred into vessel 542 (Building 21) . No ocher medium-level waste has been produced during Che

yeai under review; the spare capaci y of ves se l 542 remains 100 si .

During 1977, no high-level watte has been produced. The l iquid in vesse l 253-lb has been kept aC about

40*C; the air sweep in the vessel has been kept at 20 Ntn / h . Between April 27, 1976 and January 3 , 1978, 3

in a l l , 4.65 m of water has been evaporated from the low enriched waste concentrate (LEWC) scored in

vesse l 253-lb, corresponding to an average evaporation rate of 0.31 1/h.

The following table gives an • verview of the liquid wastes in the various storage tanks, at Che end of 1977.

Situation in the Storage Tanks

b u i l d i n g

n o .

21

21

21

21

21

21

24

24

24

24

5

5

22

22

lane. n o .

541

542

543

544

545

546

540.10

540.11

540.12

540.13

25... 1a

253.1b

258.1

258.2

Use fu l

Capac i ty

(ra3)

250

260

260

2B0

260

260

500

500

500

500

40

40

210

210

Type of

Waste

HWC

HWC

HWC

Su I f ex

Sulfex

AluminatB

-HWC

HtWC

Zirflex

LFWC

LEWC

HEWC

titWC

V o l u m e

t m 3 l

255

164

257

260

143

151

-500

500

394

29

36

174

131

u (Kg!

1.283

126

34

25

-363 »

36 XX

526

24

48

1

1

Pu tg)

6.368

730

580

185

-3.790

990

3.047

700

1.B90

537

270

Remarks

7 .300 Kg s t a i n l e s s s t e e l

7.400 Kg s t a i n l e s s s t e e l

1 .970 Kg aluminium

22.300 Kg aluminium

4.300 Kg z irconium

10.175 Kg aluminium

6.04C Kg aluminium

-, -,- r Z 3 5 ' t X 2 . 3 ; i i f J .

- . _ 235.

6. 2 Bitumlniiation Facility

Status

The Bituminization Fac i l i ty was ready for active startup at the end of 1977. In Lhe beginning of 1978,

a preliminary active test run wi l l be carried out with one slurry batch of about two cubic metres, contain

ing a 10 Ci of Au spike. Active operation wil l then be started with the incorporation of some aluminium

jacket decladding waste batches, prior to switching to normal medium-level waste incorporation f lowsheets .

Modifications

In order to increase the r e l i a b i l i t y of the f a c i l i t y , numerous modifications have been adopted. Only a few

ar t îî.ent ioned below.

— In view of reducing the r i«k of so l id s beins; swept along in to the d i s t i l l a t e rout ing of the extruder, the

dur.is ol' the extruder h.ve been extended by about for ty cent i n e t r e s ; new condensers have been designed,

i'ui i t , and f i t t e d op.

25

I s view of reducing the splashing i n the extruder donas, the prof i le of the screw has been nodified

by the supplier (Werner • Pfle iderer) so as to transfer the kneading blocks fros the doaes into the

closed conaartaents of the extruder.

la view of avoiding the plugging of the discharge pipes for powder reagents , and iaproviug the nixing

ia the reaction wease l s , the resgeata w i l l no laager be added as a powder into the reagent v e s s e l s 7

ox 8 , but a s an aqueous suspension of these powders. To t h i s e f f e c t , a a i l i n g vesse l has been bu i l t

and was insta l led between the powder reagent weighing unit and the reaction v e s s e l s .

In view of f a c i l i t a t i n g the interventions and decreasing the radiation dose r a t e , several new deconta-

a iaat ioa liants have been added.

In view of improving the f i r e - f i g h t i n g p o s s i b i l i t i e s , additional spray rasps have been f i t t ed up above

the conveyors and waggons loaded with f i l l ed-up drtass.

ChaPWcal Pre trea fen t

The different cheaical flowsheets were used in preparing about f i f t y - e igh t cubic ae tres of simulated

waste; cold t e s t s were carried out , and the resu l t s were used in writing the operation annuals.

— Operation of the Extruder

The extruder was operated for roughly 1,230 hours. During the cold t e s t s , soae 3SO draw of 220 1 were

f i l l e d . Overall decoataaination factors of 10 were e a s i l y obtained. The viewing systea (endoscopes)

ins ta l l ed above each done allows renote inspection of the inside of the doaes during operat ion. After

these 1,230 hours of operation, the wear of the extruder screw eleaents was neasured. The aaxiaun wear

•ensured on the kneading blocks was two a i l l i a e t r e s .

— Uraatua gun —

One t e s t run was carried out with a slurry containing natural uraniua. In a l l , twenty-thiee d r u » of

220 1 were f i l l e d with a uraniua content ranging between 0 .3 and 0.72 Wtî- The aain problem during this

particular run was the breaking of the

safety pins of the extruder screws.

Following the suppl ier 's suggest ion,

stronger safety pins were introduced

(aaasuring eight instead of s ix

a i l l i a e t r e s i s diameter).

OviHvim on the entnudui-ivapowCon

26

P r u " tondUn»,

During th* various cold run», tha

conveyor system was thoroughly t e s t e d .

Oo several occasions, the r e l i a b i l i t y

of tha grab too l s proved uncertaia.

Consequently, minor modification» Hera

carried out in order to improve; i t .

If a cooling time of twenty-four boora

i* required before the drums caa be

unloaded into the bunker*, two waggon*

w i l l have to be used on one track. To

thi» e f f e c t , the e l e c t r i c a l aad

instrumental part of the waggon transport

system wil l be modified rather extensively

in 1978.

faxt o, {fee dium handling iifU.au be-

(utm tnWU*% lb and SuUditig lis a

taggon toadtd mitk biturJUztui diumt

ha& juAt pOMed the gatt te tkt

stotagt iacitUif.

Tne c u t e bxidgi i n Building 11 iA

tatung a bituminiztd dmm $tom the.

covudet to the itoiagt atea.

http://iifU.au

27

Tfat! ccntxoi loom o$ Smlding 11.

6. 3 Sol ld Ntstes

The following table givet an overview of the mounts of standard tvpe «olid wastea produced during the

year under review.

Standard Typt Solid Hastes Produced during 1977

Type of Waste

Combustible B"Y

Non-combustible g-y

Non-combustible 8"Y

Pu-contaminated equipment


Absolute f i l t e r s

P r e - f l i t e r s

PacMng

220 1 drum

220 1 drum

30 1 box

30 1 box

220 1 drum

cardboard S p last ic

cardboard I p las t ic

Number of Items

614

393

20

305

78

199

200

The major part of the solid wattet produced during the year 1977, and other wastes, produced previously

and accumulated onsite, were transferred to the conditioning facilitiet of the CER/BELCOniCLEAIRE.

The next table gives an overview of Che wattet which were trantferred in the courte of the year.

28

Wistes Transferral in 1977

Type of Waste

Combustible £ - f

ton-combustible g-f

Non-combustible B~y




Glove boxes from Pu-uni t

Absolute f i l t e r s

P r e - f l i t e r s

Packing

220 1 drum

220 1 drum

30 1 box

220 1 drum

30 1 box

timber case

timber cass

cardboard * p l a s t i c

cardboard t p l a s t i c

Number of Items

536

364

98

31

BOB

3

2

176

152

Ko Belgian operation of disposal of radioactive wastes into the Atlantic waa carried oat, daring 1977.

The inventory of the wastes at i l l accumulated onsite, on various locations (excluding th* wast** stored

in the ponds) is given below.

Wastes Accumulated Onsite

Type of Waste

Combustible 0-y R < 200 mR/h

Non-combustible $-f R <_ 200 mfi/h

Pu-contaminated Pu - 10,650 g

Pu-contaminatea Pu not measured

Absolute f i l t e r s R < 500 mR/h

R > 500 mfi/h

P r e - f i l t e r s R < 500 mR/h

Pu-contaminated pre-f l l t e r s R > 500 mR/h

Nan-combust ib le P > 5D0 mR/h

Combust ible R > 50C mK/ti

Ï4D g r a p h i t e j a c k e t s

Packing

220 1 drum

220 1 drum

30 1 box

30 1 box

30 1 box

timber case

220 1 drum

bituminlzed 220 1 drum

cardboard » p l a s t i c


cardboard S p l a s t i c


220 1 drum i n 600 1 drum w i t h conc re te r i n g

22G 1 drum i n 600 1 'Jrum w i t h conc re te r i n g

concre to c o n t a i n e r

Number of Items

46

5

51

162

125

3

44

14

1

1

31

10

10

19

10

3

Location

shad

shed

shed

B. 22

shed

shed

shed

shed

shed

shed

B. 4

shed

B. 4

D. 25

B. 25

Ë. 25

Type of teste

Résina and diatoms [water treatment S. 21

Qff-ga» f i l t e rs (8. 5/22)

(B. 24. Call 03)

Unidentified wastes

High dose-rate shipment

Conerate-conditioned wastes R > 0.5 R/h

Obsolete LLW piping to CEN/SCK

Pocking

concret* container

concrete container

concrets container

concret* container

concret* container

concreted 600 1 drum

none

Number of Items

14

5

9

99

4

45

3.400 m

Location

B. 25

B. 25

B. 25

B. 25

a . 25

B. 25

outdoors, wast of B. 21

7 PROCESS CONTROL LABORATORY

7. 1 Personnel

Personnel assigned to the Process Control Laboratory consists of one group leader, three shifts of each

one supervisor and two analysts, and one laboratory assistant.

7. 2 Analyses

During tb* year under review, 4,900 analyses were carried out by the PCL. This number can be broken down as follows:

— 1,000 analyses of decontamination solutions fro» the plant, water fro* the ponds, and liquid wastes;

— 3,300 analyses of cold-test samples fro» the bitiasinisation unit; 500 analysée of high-level waste saaples; 100 analyses of Raschig rings removed from different tanks.

Moreover, 520 standard determinations ware carried out in order to check used analysing methods, and in connection with the Eurobitum analytical process training programme 580 tests were carrier1 out, which makes for s total of about 6,000 analytical determinations.

The intensive treining programme on the analyticsl methods for operation and process control in tb* bitu-minisetion faci l i ty started in 1976 and was continued through 1977. In addition, differential thermal analysis training was conducted with artificial , inactive alurry compositions simulating the slurries which are expected during active operations of the bituminisation unit with real Eurocheeic MLW stramme.

7. 3 Equipment

Apart from a few final modifications to the slurry-sampling system and to the room ventilation, the laboratory equipment for the sampling of the various waste solutions, the slurries and the secondary waste streams, nid for some direct process control analyses was set up in rooa 010 of Building 26.

JO

Th* recuits of tb* bitoaen-iacoiôratad produce (NP) taaplieg taata proved uaiaatia-factory «baa blow bitaaaa of tb* aexphalt B,5M0 typ* vaa aaad.

A aocood ayataa ia being aiaainad aad will b* fitted up bofor* bot startup, ia order to allow IIP •sapling with aap typt of aaaphalt expected to ba «aad ia tha bita-aiaiaatJia procaaa.

The high-level waate aaapliag ayataa by aaaaa of caadrilloa aad abialdad bliater waa fitted ap ia Building 3 aad waa already naad for UWC aad Kawt aaapliag aad aoalyaia.

With regard to tb* decontaaicitioa aad dieaaatliag progrès** ia Building 3, the whole eauipaeat for taro-bitua feed aad product aoalyaia had to be reaoved froa that bailding. A coaplete laboratory aad counting rosa «,» iaatalled ia Building », wbera the Iwrobitwa-feed aaalyaaa will bc carried ci t . Saaplaa will ba transferred by aeaaa of a direct, pmuaatic aaaple-traaafer ayataa between rooa OIO of Building 26 aad Building 8. praliaiaary work for tb* aaalytical laboratory for bitvaen-iacorporated product coatroi waa (tarted in rooa 112 of Building 10.

7. 4 Dtcontttlnation

Preliainary work for tha intensive decontamination aad cleaning progress* for Building 3 waa atarted. four boxee ware reamed froa the boa chain in room* 137, 136, 133; eleven boxe* ware cap tied aad docoa-

2 taninsted to an inside a-coataaination level of lea* than S dpa/ca (aaear teat*).

Th* unshielded box chain of the Procaaa Control Laboratory in Building 3 wa* eaptied and i* now ready for dismantling. The shielded boa chain wa* rinsed aad alaoat ready for eauipaant reaoval.

Sia of th* sixteen ahitlded bo»** «t i l l need additional decontamination in order to lower the radiation field at tb* inside to a ptraiaaibl* level. Half of the shielding of the boxes we» reaoved and cleaned for inactive storage outside the controlled tone.

Flushing and decontamination of th* hot-vast* piping systea in th* baseaent of Building 3 wa* started.

i

j View on the iiUudt ci a ilu.iiij sampling btiMvi, with ' pti cenVicl tyttem Ue$tl , glaii CMCutaticn pcti fci

iampLiHQ legnttt), and pitciiû'n fcdiatice ici centufaijc

INTERMEDIATE STORAGE OF LOH-LEVEL SOLID HASTES

31

i PURPOSE

Building 23 baa baan raised for tba storage of druas containing low-level aolid v a s t e s , which are

presently stored outdoors o a s i t t .

Part of tb* solid-waste conditioning shop w i l l be aoved into the new bui lding. The old waste-tranfer

l ine fro» the low-level l iquid waste treatment s t a t i o n to the CEH/BELCORUCLEAUE Waate Treatment F a c i l i t y

which i s presently kept outdoors onaite w i l l be cut up and packed for subsequent storage i n t h i » building.

2 OCSCRimON

The itonagi CcuUtUy {o\ îaw-tnel iotid ua&tu ISaltcUng 23), umfe/t cumViacU.oti.

Building 23 is located to the north of Building 21; i t s lengthwise axis is at right angles to the bitu-minization facility; ita diasnsions are 60 • in length, I* a in width, 6 • in height. It ia a prefabricated concrete construction which can be divided into two sain parts:

2 — the storage area (40 m x 14 n - 560 m ) ;

— the waste conditioning area, including unit! for cutting and compact ing of non-combustible «olid

vattct; compacting of combustible solid wastes; decontamination in view of maintenance; concrete em

bedding; measuring of Pu-content; ventilation, and change room.

32

3 EQUIPMENT

HANDLING of the di f ferent waste -turn» v i l l be performed by mean» of a l i f e truck.

COMPACTION of the non-combustible wastes wi l l be carried out by Beans of a multipurpose hydraulic press

with an hydraulic piston of 250 t .

CLTTINC-l'P w i l l be carried out by neans of a mechanical saw, whenever poss ib le .

Both the above aencioned press and the saw have been aainly designed for the cutting-up and compaction

of the old waste-transfer l i n e .

COMPACTION of the conbustible wsstes w i l l be carr .ed out by a pneumatic cy l inder .

DECONTAMINATION of equipment from the bituminization f a c i l i t y w i l l mainly be carried out in a decontami

nation basin measuring 3.5 m in length, 0.8 a in width, and 0.6 m in height, and presently under construct

ion. Two already ex i s t ing ultrasonic basins w i l l alao be instal led in the decontanination room.

CONCRETE EMBEDDING of the w?ste into druas w i l l be carried out on a vibrating tab le ; the concrete s ixer

and the conveyor screw w i l l be set up outside the drum-filling rooo.

MONITORING by scans of a Pu-B*asuring device w i l l be carried out in order to detect any possible plutonium-

content of the waste which i s being handled.

4 VENTILATION

Two independent v e n t i l a t i o n c i rcu i t s are being planned: one to ensure vent i la t ion of the storage area and

consisting of an exhaust fan and an absolute f i l t e r casing; another c i rcu i t for rooo v e n t i l a t i o n , ensuring

the required depression and air changes in the operation rooms.

5 STATUS OF THE PROJECT

Construction was started in October, 1977, and finished in December, 1977. Ins ide , c i v i l engineering in

the different rooms and on the floor slab was started in the middle of December, 1977; i t i s scheduled

to be finished by the end of March, 1976.

An invitat ion to tender for the construction of the venti lat ion system was sent out at the end of 1977.

Piping, e l e c t r i c i t y , and equipment v i l l be instal led by Hurochefflic personnel.

M

LAIOüT OF BUILDING 23

à © / @

2nd floor

ij- ® @ ®l

®

F6E^T@ n

l i t Floor

01

02

03

04

OS

06

07

Storage Hail

Cutting and Compaction

Compaction of 'on-combustible Westea

decontamination

Concrete Embedding

Change Room

Corridor

ce 09

10

11

12

13

14

Office

Plutonium Measuring

Ventilation

Fi l ter Room (2nd floor)

Storage Room (2nd floor)

Concrete Mixing

Cellar

GENERAL SERVICES

35

1 PERSONNEL

During the year under review, toe staff of tbc General Services Department (GSO) increased by one

member, a deputy department bead, who joined the Company as fro» October I , 1977.

The s taff cam be broken down a* fo l lows:

— Department Haai I

— Deputy Department Head I

— Quality Control and Papers («) I

— Stores 3

— Mechanical Workshop and Pipe Fitters 10

— Mechanical Maintenance i

— Utilities S

— Civil Engineering J

— Instrumentation and Electronics t

— Electricians *

— Instrumentation Shift 3

(•) A secretary was shared with the Plant Operations Department.

In addition to the Company staff, the following outside personnel was hired:

— Permanently, two highly qualified argon welders for all purposes;

one electrician to replace a staff member who has been ill since 1976;

one fitter for the Research Laboratory.

— Temporarily, since mid-October, 1977, three technicians from the Supplier

of the crane in Building 27 (Eurostorage) to assist with the startup of

the facility, and to get the electronic spare parts ready

2 MAIN TASKS

The following paragraphs summarize the main tasks performed by the CSD staff during 1977.

2. 1 Mechanical Maintenance and Workshops

Routine maintenance of the ventilation system, the pumps, blisters and other equipment in Che process

buildings, and of Che handling devices in Che Fuel Reception and Storage Building were carried out as

usual.

Dur inn 1977, however, the most time consulting tasks were the completion of the alterations to the

bitiimtnization unit proper and to Building 8, in view of putting up a special analytical laboratory

for the Kurobitum project on the one hand, and alterations Co the cranes and other handling devices

tor the hurostorage project on the other hand.

Two mechanics were continuously busy in the workshop of the Research Laboratory (Building 10).

)*

2. 2 Maintenance of the Site

This group carried out routine maintenance of the buildings and the site grounds (roads, gardens» lawns)

and spent the rest of their time to the handling of heavy pieces of equipment and waste drums, unloading

trucks, assisting sub-contractors, performing small engineering work, pointing, concreting, painting,

and generally assisting the other group» of the Department-

2. 3 Instrumentation, Electricity, and Electronics

In this group too, most of the time was devoted to works for the Eurobitum and Euro»torage facilities:

completion and adjustment of control and monitoring system*, and finishing of the electrical installations

in Building 26; revision, repair and completion of the electrical installations sad replacement of the

laser control system by coaxial cables on cable drums.

The instrumentation technicians for the process buildings were again working in shifts, in order to

ensure the maintenance of the installation required for measurement and control of the process equipment,

and in view of rendering assistance to the possible startup of the waste-conditioning facilities.

In the short remaining tine, the electronic equipment of the laboratories was repaired and maintained

as far as possible. Moreover, the public address system and the telephone installation were kept in

good working order.

2. 4 Stores

Work in the three stores (general, mechanical, and chemical) consisted of maintenance, ordering, and dis

tribution of materials and spare parts, and stocktaking.

2. 5 Contracted Services

Outside firms were contracted for special maintenance jobs and materials, or following a legal obligation

(e.g. inspection of lifting devices, chains, ladders and the like by a specialized body).

Outside firms were also contracted (or the periodical maintenance of the l i f t s onsice and in the residential

quarter, the telephone installation, the heating regulation system, the emergency power generator, and

the inside and outside cleaning of the buildings.

i WORK ORDERS

A summary of the moat important work orders carried out during 1977 i s given below.

FOR THE PUNT:

— modification of some fan motors allowing star/triangle startup;

— renewal of the heat exchanger of the central heating system in Building 3;

— manufacturing of new .'eedle blocks and spare parts for existing needle blocks;

Both pictunet thon a gutat deal oi twiciktmic't GSO CAaitmnthip, itcuAtd {«« the, i iactwuxQ oi thi* inteAphate oi tht bunkt* xoU buiige. Ivitm item tht top i* upptn phot»}. Tht petition iinaing infoiunaticn it tMUHieMtd fit* tht tante* te tht dut* pAoctUinf tytttm uut tht contxol loom by mean* oi thit coaxial eabtt tytttm en atbtt dKtmt (Xfcc tatttA. u located to tht Itit oi tht upptn photo) xiptaciitg tht otiaixat U*tA eenViel tytttm mhich pnovtd too pttcitt to utt uUhout coiitimout pxebttmt. Tht tern* phote it thawing uhich complexitiet ate inttalttd into the ttteJt cytindt* you am teg. en tht light oi the upptA pictuxt.

JS

— construction of new valve extension handle» foi th* valves ut the NW evaporator in building S;

— frequent repairing of heating devices Primary Supply I and 2 in Corridor fc.OJ of Imildimg I;

— general maintenance of motors, fans, and vent i la t ion System;

- - manufacturing of s t a i n l e s a - s t e t l casings for off -gas vent i la t ion in buildings 5/22;

— manufacturing of a new Manual flap in the IDE (high depression exhaust) duct after fan 2*4-3i> ii. BO.01;

— replacing of part of the carbon-steel vent i la t ion duct after fan 2>*-îb in Corridor b.OI;

~ intervention in Cell 0* to r ewe Id cut l ines and s l i g h t l y a l ter ing i t ;

- - revis ion of the b l i s t e r s in the Plant;

— revis ion of y-monitors in Buildings 5/22 and 8;

— maintenance of the instruments in the plant;

— connecting the nore important alarm units to the guard house;

— replacing lb* damaged e l e c t r i c a l switches and socket o u t l e t s in the Plant bui ldings;

— repairing of e lectronic equipment in the Plant and the laboratories;

— connecting the heavily shielded glove box no. I in the Analytical Laboratory (B. ) ) to the power grid;

— painting the v e n t i l a t o r s 2S4-bb and the spare ones;

— putting up the intervention cabin in front of the Solid Haste Pond <(. 2 ) ;

~ removal o f contaminated concret* and PVC in Gallery In .04;

— repairing of contaminated floor l ining in Room 126 (B. 3 ) .

FOB WILDINGS 26 AW 27

~ ins ta l la t ion and adjustment of the >-detectum for bitumen-incorporated ((IP) sampling;

— ins ta l la t ion of a heating system in the vent i la t ion duct for building 27;

— i n s t i l l a t i o n of platforms on the bridges of building 27, improving working conditions when repairing

mechanical and e l e c t r i c a l parts;

— aanufacturing and putting up a system to remove and replace the extruder axes;

- - altering the e lectronic control systea of the bunker cranes by replacing the lasei control system by

coaxial cables on cable drums, improving control;

— ins ta l la t ion of additional f i r e - f i gh t ing equipment in Ce l l s 005 and 013;

— manufacturing and ins ta l la t ion of a s t a i n l e s s - s t e e l dome for slurry feed;

— a l terat ion uf the extruder o u t l e t ;

— ins ta l la t ion of the steam traps of the c-Atrudet in ROOD 012 instead ot Room OI<r;

— repeated repairing uf the nixers for three v e s s e l s in building 2b;

— ins ta l la t ion of a system to operate s ix valves in Room 012 from Corridor 04 under the condensers;

— several jobs in buildings 26 and 27 l i s ted on a punch l i s t ;

— concreting the remaining openings in Building 26;

- - painting the wal ls and doors of building 26;

— ins ta l la t ion of the heating system and connection of the sanitary apparatus of the change room in

Building 26;

— ins ta l la t ion of floor drains in the two bunkers of building 27;

— manufacturing spar* printed c i r c u i t s for the bunker cranes;

— finishing the e l e c t r i c a l ins ta l la t ion uf the change room in Building 26.

)•

FOR THE RESEARCH DEPARTMENT:

- - several jobs in connection with the Pamela project;

— manufacturing of containers tor g l a s s bead»;

— cod i f i ca t ions of Hot Call no . II;

— installation of a f i lter casing in lot Cell a». II;

— manufacturing of a miser s e t t l e r (Curswatt projec t ) ;

— manufacturing of cool ing jackets for the Joule-heated Be l ter ;

— adaption of the disingsgamnr, column to the f l s i d i c bad reactor;

— construction of an electricalIT heated calciner;

— several jobs for the Gelsenhnrg Cnapiay;

— repair and naiatenancs of the e lectronic equipment;

— installation of an electrical furnace;

— f i l l i n g the shielded door of hat Cel l no . II with concrete;

— a l t e r i n g the conference roam en the ground f l eer into a printing o f f i c e ;

— altering the aediun-level waste lines in the Pilot hall;

— replacing and repairing damaged Venetian b l inds .

FM TIE HEALTH AKD SAFETY D&AHKsT:

— aanufsecuring of ten jumbos (constant a ir monitor»);

— repair and aaintenauce of monitors and ether electronic equipment;

— i n s t a l l a t i o n of v-meuicers i n building 2b.

FOR OTHER PCTARSHEaTS:

— renewal of the drainage pipes on the roof of building 14;

— maintenance and repair of the sanitary in s ta l l a t i on of the res ident ia l quarter;

— codi f i cat ion of the water treatment valves;

— repairing of the roof of building 12;

— maintenance of the elactrical installation of the residential quarter;

— improving the overall e l e c t r i c a l i n s t a l l a t i o n , following remarks by the A l l (Associat ion das

Industries Belges) inspectors;

— manufacturing of tables and benches for the change roam in lu i ld ing 9;

— maintenance of the roads and gardens ons i t* , in the res ident ia l quarter and around the canteen;

— removal of non-industrial waste;

— removal of the rott ing woodwork outside the canteen building.

-o

BREAKDOWN OF TIME SPENT

Tne breakdown of time spent by CSD personnel, excluding the group leader* and the f ive u t i l i t y operators

working in s h i f t s , i s shown in the table belov.

: • - > : ,

r . : . : • • • - ,

-' \: - 7

-.,, - i . - i i

7v«.

- -•>

-..,•,.'. . jp * . f~ ; .« r

_ct 7„r

.c « r . t . o r

r'.A» !"„•',•

::.:_ fc:\Lu-:-

I ~ T ' . S r

<;;;* 'S? 2

« 6 4

bse

6 1 . "

:SB

032

435

5 3 ?

51- ; 6 4 0 ,

6 . 3 J E '

r i r e c

-

43s

542

45J

72

1.50/

t'

: - J : J :

I;ÏÇ

ÇÛ4

V 7 .

J 5 4

1 . 0 . "

1 , 1 5 4

M

T . 1 4 5

556

532

6 1 . '

540

c i . 4 4 2

É L 5 C T B . i

Ûk".

1 . S M . - C

1 . 4 1 4

i.E20.rs

1.-153

1 . 3 4 3

1 . 4 7 1

9 4 1

mi

1 . 6 6 2 . 5 0

1 . 5 3 6

1 , 3 3 0

1 . 3 7 4

1 6 . 3 6 2 . 2 5

tviïsin.

' i l r ed

J ZC4

j ïbà

j 168

I2C

! 152

! 176

Î 152

1 104

160

• tec

; 126

[ 104

1.316

t o t a i

1.773.50

1.702

1.788.25

1.473

1.4S5

1.647

1.033

766

1.822.50

1.636

1.516

1,478

18,276.25

MlCMAfltLAL

Own

2.100

2.02a

1.625.75

1.701

1.666

2.190

1.124

1.376

2.196

1.800

1.S85

2.090

22.103.75

WGPkSHGF

h i r e d

3 4 8 . 5 0

4 5 9 . 5 0

7 6 6 . 5 0

5S4

ÖÜ1

8 3 9

3 2 1

6 2 7

4 7 5 . 2 5

4B2

4 4 3 . 5 7 .

3 8 5

5 , 6 2 3 . 2 5

t o t a l

2 . 4 4 8 . 5 C

' . 4 6 7 . 5 0

2 . 5 3 2 . 5 0

2 , 2 9 5

2 . 5 6 9

3 , 0 2 9

1 , 4 4 5

2 , 0 0 3

2 , 6 7 2 . 2 5

2 . 2 6 2

2 . 4 2 8 . 5 0

2 . 4 7 5

2 8 . 7 2 7

3„

4

4

4

4

•: < 2

3

= 4

4

4

......

a c 4 . ; '

7 . i3 .< '

J ' - . ' :

3 3 2 . 7 .

: c - i . -

? 3 ' ' . 7 L

3 2 6 . 7 7

' -•34. '

5 5 2 . 7 5

57 .77

5 T . 7 7

. 5 , 7 . 7 7

5 5 . 4 4 7 . : . .

The breakdown of the work orders carried out during 1977 i s given in the table below.

GROUPS

C i v i l Eng ineer ing

I n s t r u m e n t a t i o n

Mechanica l Workshop

TOTAL

TOTAL HOURS

6,442.00

16,278.25

28,727.00

55.447.25

NUMBER OF WORK. ORDERS

EXECUTED

159

201

371

731

I N PROGRESS

35

40

80

155

Between January I, 1976, and December 31 , 1977, the a l terat ion* to and coapletion of the Lurobicum ami

Eurostorage f a c i l i t i e s (Buildings 26 and 27) required:

37,625 working hours from the Mechanical Workshop

27,095.75 working hours from the Instrumentation Group

4,062 working hours from the Civil Engineering Group

58,782.75 working hours from the General Services Department

Provided no new problems wi l l a r i s e , these f a c i l i t i e s wi l l be started up by mid-February, 1978.

A summary of the preceeding tables i s given on the next page.

Summary of Time Spent by GSD Personnel

.- r - - i . lr •. ! ' .

•>.'<.' : - > - - ! - • : : ' i . - L i t

. : • . . . • : - • : : > • . . 0 1

,. .. .

I ' . J . I : ^ r u l ^ . a Ju t

*> : ! • ; • • •' J -.Jt'^t^ J p t

> ! . - i - ' . . i " ; j . t i ' - r . t ^ . "

~ •• • : I - T " . : 1 .,_.iri. ':=r'

••ü.v'- ir n e : ^ J : Curage

H : : , ^ : - : , -

! ; T - L

Li IV I I S-.MGINEtklM;

nours ana *; o ' t o t a i

2 ,579 .00

3 0 . 5 5 *

1 .222.50

14.48*.

:üb .üc

1 . 2 9 i

3S2.U0

4.52*.

)2.00

LI .Jd*

9 1 . DO

1.3B*i

JOü.SC

a. ' ib- .

3 . 7 1 3 . 5 0

43 .99 ' .

12.50

3.1 j».

J . - 4 i . . j J

INSIRUMrNTATICJN

hours and \ o f t o t a l

1.B11.26

3 . 9 U

3 .997 .25

21 .8 7-.

652.-JO

3 . 5 / ' .

9 7 4 . ; ' ,

5.33",

726.30

3.97*.

LT-b.ün

I ,2fK

. '9.00

0.16'-

9 .320 .00

r.3.73».

3 / . 50

.. . IS* .

18.270.:- ' -

rltCHANICAL UQHK.SHÜP

hours âne: \ of t o t a l

3.142.SO

10.94*.

5 .789 .50

20.16*,

111.00

0.39*.

3 .997 .00

13 .911

276.7b

0,96*.

94 .50

a. 33' .

29E.bC!

1 .03 ' .

14 .216 .7E

49.43 ' .

ac2 ,bo

2.734

28 ,727 .00

TOTAL HOURS

AND '. OF TOTAL HOURS

7 .532 .75

13.59*.

11.QC9.25

19 .65 ' .

872.5D

1.57».

5 ,353.75

9.65%

1.034.75

1.Ü7*.

420.bU

Q.76*.

626.00

1 .13 ' .

27 ,750 .25

50.05*.

647.50

1 .53 ' .

56 .447 .25

fWi-Yt M.

AT 1.HBU H/Y!/->'

4 .4b

6,bb

0 .51

3.10

0.51

0.25

0.37

16 .51

0 .51

32 .96

int !>n.ii spent by the executive staff members (I Department Head, 1 beputy Departnent Head, S Group Leaders), 1 quality controller,

.tor.' weepers, I secretary shared with the Plant Operations Départirent, and 5 utility operators (365 x 24 hours) are not included

;. -(.*s -i/«i.--ry rabve of uim.' ïtc.t.

http://29E.bC

COr«Si'MFTU;% Oh UriLITItS

i>urini; 1477, the cunstiuipt ïov or u t i l i t i e s was Lhe fol lowing:

St eaçi (del ivered 6y tBLS): 3 i , lö7 t .

The average pr ice in 1977 was 310 Belîin francs per tonne, as compared to 3.1 ^. , - , -d^ pr iii.j 01

327.70 bF/t in 1976.

t U c t r i c i t ^ U e l i v e t e d by LBfcS) : 9,IUU.8!>0 kWh.

The average pr ice in 1977 was 1.486 BF/kWh, as comDared to an average p r ie? 0i 1. i6f> BF/*i.V in

1976.

[ii . tered_vat.er (own product ion) : 174,880 m .

SïiSiüüEîiSîi-ï3 1-" ( l , w" product ion) : 1 ,h83 m .

3 2Ei2-_iï8-*:ïEïE (del ivered by PII>PA) : 1,635 m .

Nitrogen: Nn consumption.

Ç0.EÎE£Ë££_,É__,iE:

Is normally produced by one compressor with an output of 1,000 NIÎI / h ; it «at. oêrar.ed, jr.iy

p.-irtlv under load, for 8,700 h.

Thr twi' u iese l genera tors wert r egu la r ly tested .it fu l l cr.arR._-; these t e s t t tf^k half H day

each month.

http://ii.tered_vat.er

http://cr.arR._-

INDUSTRIAL DEVELOPMENT

4 Î

Suriag 19??, cm industtial deveUisnint activit ies have been primarily devoted «a s o l v i t Eorocheoic's

problems ia tha f ie ld ot ta* sol id t f icat iea of high- aad aadima-level liemid wastes, ta» ceaditioatR*

of set id vaste*, ana the treatment of organic solvent wastes.

These act iv i t ies , carried oat accord ins; ta Ear ec hemic's "baeic" devel J pen at programme, caaaisted,

awre specifically, ef:

—• tba solidification ef KVC (highly eariebsd waste camnatcato) by mamma of ta* L0TES process;

— the treataaat of speet aalveat by aeeae af tb* sarawatt pcacaaa;

— tba treatment of platoaiaai haariag aal id waatas by tba taaaaatcaab process;

— the conditioaiag of highly activa eea-caeauecible aalid wastes by iacecporalioa iate a pelymer-cemcrete

aatr is .

la addition to this basic prngi a — week» davcleeaaat act ivi t ies have aaaa carried out ia application ef

a contra-t with tba Celsewberg Ceaeemy oa the aal idif icatiea of rutaa-tvaa high-level lieaid waste frea

toemercisl reprocessieg plaats by meaaa ef tba PalnttA process.

This contract has beeo terminated at tha end of 1977. aafatiatiaaa ia view of concluding an agreement on

the damoastratioa of the technical feaeability ef tba NietlA process are aeatioaad ia aabsectioa » of

chapter 1 of the présent annul 1 report. A eaw three-years develeemeet programme haa bean established

between Gelseaberg aad Eurocbemic, becoming effective at tba befianiag of 1971, but « i l l availing

approval by the hoard of Directors.

1 SOUDIFICATIM AM COHtlTIOllIIni OF LIQUID MIwH- i im a*STES (LOTES PROCESS)

In Deceaber, 1*76, the board of Directors had decided to apply the LOTES process for the solidification

of Eurocbeaic's high-level wast*, coasistiag ef abest MM) cable w i res of aluminium watte ( K I K ) , and

70 cubic n t b c i of Paras waste (LEK). Consequently, the development work during 1977 has bean devoted

to optimise the LOTES process caaditieas ia view of writing oat invitations to te- der for engineering

services end choosing the approp iate architect engineer.

The aain tasks carried out in relation to the LOTIS process were:

— i t ; determination of the chemical flowsheet conditions of the LOTES process for the treatment of

F.urocheaic's HEWC,

— the vrit ing oat of an invitation t». tender for engineering services, aad the evaluation of the

resulting offers;

— the demonstration of the LUTES process is inactive pilot-scale equipment;

— the optimisation of the prccess conditions for converting the phosphate calcine to a phosphate

rerauic product in a Joule-heated setter.

1. 1 Chemical Flowsheet of the LOTES Process

The figure on the nexr page thou» the chrmical flowsheet of the LÛTES process for the treatment of

uirocheaic's HLWC (80* m >

The ana ly t i ca l dettr:r.ina'_i.>n or the exact chemical composition of the HEWC, performed during 1977, has

been most helpful in th i s respect («^.g. the free a c i d i t y in the so lu t ion turned ou', to be s u b s t a n t i a l l y

lower than expected) .

The flowsheet below ind ica tes the following s t eps :

de s t r c t ion of free n i t r i c ac id , and reduction of mercury to the me ta l l i c s t a t e in a batch evapora

t o r , using formaldehyde as a reducing agent ;

separat ion of mercury and concent ra t ion of the HEWC s o l u t i o n ;

— conversion of the concentrate t3 phosphate ceramic granules containing sodium-aluminium and phosphate

in a nearly equiraolar r a t i o ;

melting of the phosphate granules in a Joule-heated inci ter ;

s o l i d i f i c a t i o n of the melt ;n a s t a i n l e s s - s t e e l c a n i s t e r .

1- 2 Inactive Pi lot-scale Tests of the LOTES Process

Separation of Mercury

While inves t iga t ing the den i t r a t i on of the HEWC so lu t ion wi th formaldehyde, i t turned out t ha t mercury i s

e n t i r e l y reduced to the me t a l He s t a t e at the moment the f ree n i t r i c acid i s des t royed. During these t e s t s ,

i t was demonstrated tha t l iquid mercury can eas i ly be pumped out of the evaporator by n.eans of an a i r - l i f t

n- QÜ42É 7- O-

• MLW

THE V.OTES PROCESS FOR TREATINÜ EUROCHEMIC S M E WC

!*" '*' .1*1.

V

45

device to a height of tome two metres. The t e s t s further shoved that an ac id-def ic ient aluminium

solution containing 70 g Al/1 was obtained, implying that the HEVC feed solut ion i s concentrated by a

factor of 1.5 under continuous denitration at 100'C. The process conditions have subsequently been

adapted to enable the mercury separation during th i s denitration s t ep .

The external ly heated stirred-bed calciner with an average capacity of 3 1/h has been operated for more

than 2,000 hours, producing phosphate granules of 1-3 an in diameter suitable for the demonstration of

their conversion in a Joule-heated melter.

The n i t ra te content of the calcine can be reduced to l ess than 5 WtX if the calcining conditions are

correctly applied. The calcination of preconcentrated HEVK, as scheduled in the included f lowsheet, has

also been t e s t ed . It turned out that th is process i s not giving r i s e to troublesome p. l e n s .

It turned out that a product which i s almost equimolar in sodium, aluminium and phosphorus y i e lds a

solid with the best properties for intermediate and long-term storage, when melted.

Via» o$ the 16 UXnt

Jouli-hvUid muÂXeA ijo*

thi ccnveAiwn oij the.

Ai-Na-P giawltA to a

gla&i-ciAAmic product.

—- Conversion of Phosphate Granules to Class-ceramics —

The conversion of the alL,inium-sodium-phosphate granules, produced by the fluid-bed calciner to a g l a s s -

ceramic product, has been demonstrated in a 16 l i t re Joule-heated melter. In a l l , the Joule-heated melter

has been operated for more than 1,600 hours.

By determining the v i scos i ty and the e l ec t r i ca l resistance of the melt as a function of the melting tempe

rature (about I,000-1,500°C), the optimum glass composition could be found. The corrosion rate of the

refractory-material and the electrodes of the pelter has been c l o s e l y followed. From these t e s t s , we may

conclude that SnO., has a Higher corrosion resistance than molybdenum.

Th* ravltiug tes t s have yielded numerous

üatj on the behaviour of the equipment

material, the quality of the result ing

glass-ceramic, the configuration of the

e lec trodes , the melt-discharging system,

and the temperature-control system. The

results allow the demonstration of a

1 : 1 scale Joule-heated melter with

a capacity of 200 I to be started. The

same capacity would be required for the

s o l i d i f i c a t i o n plant treating Euro-

chemic's high- level wastes.

teiynbtt/ $ct hot leach tut* c$ XiL-P

aiiinui&j. Aj^ct bcctoig dittos) a ceA-

ttuti turn, tkt diitM-Hd >ua£ct i& atia-

Ciztd ici St, C«, fo , Zi, Ru, and At1U.

ggpduçt Characterist ics —

LEACH RATE: The leach rates of the various LOTES products, d i s t i n c t l y varying in chemical composition

and produced under dif ferent process conditions» have further been determined.

It i s worhh mentioning that the method used in determining leach .ate» has s'gnificar.r !y been improved

by applying t.ie method the IAEA has proposed recently and by determining the surface exposed to leach

ing more accur . ' e ly .

—6 —7 —2 —I The LOTES products show leach rates between 10 and 10 g.cm .d , IAEA standard method.

as defined according to the

PHYSICO-CHEMIl ',L AND MECHANICAL PROPERTIES:

Numerous thermographic analyses , thermo-

conductivity measurements, d i la t ion and

X-ray analyses have been carried out upon

the produced LOTES samples. The main

mechanical analyses performed are the

compression strenght, the shock res i s tance ,

the Brinell hardness, and the thermal

shock res i s tance .

.IICR0SC0PY: In cooperation with the CEN/

SCK, Mol, and the Inst i tut National de

Verrerie (National Ins t i tute for Class ) ,

Charleroi, two techniques have been

diveloped for the invest igat ion of the

surface condition by interference

contrast and by thin layer microscopy

identifying the crystals in the pro

duced glass-cersffiics.

47

The pictures on this page show how part of the cristalline phase has been transformed to the amorphous

phase by prolonged heating at the melting temperature.

1. 3 Invitations to Tender

Four European architect engineers were

invited to tender their engineering ser

v ices in view of conceiving and design

ing a high-level waste s o l i d i f i c a t i o n

f a c i l i t y based on the LOTES process.

These tenders have been evaluated r e

la t ive to their competence on the spe

c i f i c technology used in the LOTES

process. None of the tenders showed any

considerable nuclear experience of the

fluid-bed technology, nor of the Joule-

heated melting. One of the tenders,

however, included a detai led conceptual

study indicating an interest ing a l t e r

native for the melting step: i sos ta t i c

pressing of the phosphate granules.

In order to obtain a profound evaluation

of the LOTES process, Fluor Engineers

and Constructors Inc . , Southern California

Divis ion, were asked to examine the com

mercial f easab i l i ty of the LOTES process

for the treatment of:

— Eurochemic's high-level waste at a

capacity of 200 m per year;

— coitmercial Furex-type waste at a

production rate of 30 m per year ( in

view of possible future needs).

The study concluded that a LOTES plant

can be designed from Eurochemic's labora

tory and p i l o t - s c a l e t e s t s .

Top picture ihtmii güut-cetamic motten

cU 1,225'C $0* apploxUmateiy 1 houA..

ilnte%ieA.ence confuut; ZOO xl

Loufi pictute ihoua the influence of, the

htatuxg time on iize and volume, faction

<J< the ciiitûMine phMe in a photphtUe-

glaii ceAamic with a mote Mitic o$

1.2 : ! : 1. Haf Ufa Vs (Infe/lêieMce tonXACUtt; ZOO x)

Fallowing thus* conclus ions , i Jd i t ionu! laboratory umi p i lo t - s ca l e ' data are de s i r ab l e in order t o

>ptiris» the cqiiipr.t-nt s i z . s . l i t is add i t iona l information can be inputted i n t o the design wi th in «n

est imated ;i*;riud ot b-B souths».

Due to the an t i c ipa t ed t r ans f e r of Eurochemic*s i n s t a l l a t i o n s to the Belgian A u t h o r i t i e s , who prefer

the app l i ca t ion ot the i n d u s t r i a l l y more advanced AVM proces? (Atel ier de V i t r i f i c a t i o n de Marcoule)

developed by the French Commissar Lat à l 'Energ ie Atomique, the Board of Direc tors has decided to

discont inue research and development work on the LOTIS p rocess , as from the beginning of 1978.

1. 4 The International R 4 D Programme

During 1977, no d e f i n i t i v e agreement could be concluded on the re la ted In te rna t iona l It i D Programs*

mainly applying t o the prepara t ion of Purex-type h igh- leve l waste ca lc ines and v i t r eous granules frow

l iquid h igh- level waste and t h e i r subsequent incorporat ion in to a metal ma t r i x .

However, various member s t a t e s of the OECD have shown s u b s t a n t i a l in te res t in Specific top ics of t h i s

progransae, during 1977.

2 TREAThENT OF SPENT SOLVENT (EUROWATT PROCESS)

The content of the s torage tanks o n s i t e , containing 21 IT. of spent so lvent , itas been sampled and analyzed.

Ten l i t r e s of each tank have been t rea ted in l abora tory-sca le process equipment. The maximus: a c t i v i t y

measured in the d i l u e n t phase was about 1 vC.i/ l .

After a s e r i e s of runs , l as t ing 1,400 hours in a l l . Hast e Hoy B showed a high corrosion r e s i s t a n c e dn i

proved su i t ab l e a s a construct ion mater ia l for the pyro lyser . During t h i s pe r iod , a corros ion r a t e of

-2 - i - 1 237 mg.cn; ,yr or 0.26 nsn.yr has been measured.

The d i luent phase wi l l be separated from the solvent by means of ex t r ac t ion in a f i xe r s e t t l e r . The de te r

mittation oî the var ious process parameters has been cont inued.

The opt imal iza t ion ot the pyro lys i s s tep in the process revealed that an increase of the volume r a t i o

phosphoric acid : TBP to 45 : 55 leads to -t shor ter residence time of the mixture in the pyrolyser « ia .

consequently, to an increased e f f i c i ency »f the whole process .

The Eurowatt process has now reached the phase of i n d u s t r i a l a p p l i c a t i o n . An agreement with SON, France.

has been signed, providing that .i demonstration uni t wi l l be constructed in Building 10, in view of gain

ing opera t ional experience under ac t ive condi r ions , by t r e a t i n g part of Lurochemic'JS spent so lven t .

http://mg.cn

49

CONDITIONING OF HI5H-LEVEL NON-CCMBUSmiE SOLID HASTES

( INCORPORATION INTO POLYHER-CONCRETE)

The feasabi l i ty of embedding sol id waste into polyser-concrete has been demonstrated under water, in the

Solid Waste Pond of Building 2.

Irradiation t e s t s have been continued, and have shown that the polymer-concrete i s irradiation proof for q

doses up to 10 rad. The t e s t s w i l l be continued in 1978, in order to work out the maximum allowable dose

rate .

The determination of the leach rate over a period of 300 day* has yielded an average value of

IO~5g.cm"2.d"' in samples contaminated with , 2 7 C » , ' ° S r , , 0 6 Ru, ' 2 5 S b , , 5Zr/Kb, and ' 4Ce.

. - r ious types of polymers have been tested in view of applying the polymer-concrete process to other types

of sol id wastes, such as ion-exhange resins used in nuclear reactors , and insoluble residues of effluent

concentrates produced in power reactors .

A patent application on this polymer-concrete process lias been f i led in Great Britain (see subsection

10 of the 1st chapter).

OECONTAMINATIC.'J OF HEUC SOLUTIONS

A possible alternate for the v i t r i f i c a t i o n of more than 90 volume-percent of Eurocheque's high-level 3

waste, more particularly of a l l i t s HEWC (800 m ) i s the separation of the HEWC from the f i s s i o n products

i t is containing and the subsequent incorporation into bitumen or concrete.

\ ser ies of batch tes ts and column t e s t s , using polyantinonic acid (PAA) and smonium-12-Dolybdophosphate

(AMP) as column material , has been performed on a synthetic HEW so lut ion , spiked with Sr, Cs, 124.. 141 , I03D 152/4^ . 6 0 .

Sb, Ce, Ru, Eu, and Co.

The results of these t e s t s are shown in the following table:

RADIONUCLIDE

Stront iu i r .

Antimony

LRsium

• . tü lnr .

'Jthers

COLUMN

PAA

PAA

AMP

i AA • AÏ-V

PAA • AMF

DECONTAMINATION FALTCK

I " 3

i i o 3

i la3

- •'

; iou!

LOADING CAPACITY OF COLUMN HATERIAL AFTER TREATMENT OF 800 BED VOLUME.3

0.5 moq/g

-

1 mcq/g

After the <ffluent has been concentrated and the free n i tr i c acid neutralized to 0.3 M, alt the

europium act iv i ty could be removed by mean» of extraction chromatography using TBP an an extfactant.

The ctieiaical f lowsheet, which has been

wr i t t en out on the bas i s of these d a t a ,

s t i l l has to be checked by using a real

HEWC solution.

RECOVERY OF URANIUM AND

PLUTONIUM FROM ANALYTICAL

AQUEOUS WASTES

In cooperation with BELGOKUCIEAIRE, e x

periments have been continued in view of

establ ishing a chemical method for the

recovery of uranium and plutonium from

analyt ica l aqueous wastes. In th i s r e s

pec t , Eurochemic's work has been mainly

devoted to :

— the elimination of interfering ions by neutral izat ion and redissolut ion of the prec ipi tate in n i t r i c

acid;

— the absorption of uranium and plutonium by extraction chromatography, using TIP as an extractant;

applying t h i s method, the average recovery of uranium and plutonium obtained was • 100" ami 9J-IQ0X

respect ive ly .

TREATMENT OF PLUTONIUM-BEARING SOLID WASTES (ACID DIGESTION PROCESS)

At the start of 1977, representatives of Eurocheque, of Nuke», and of CfK have toured the United States

of America for exploration and inquiry on experience gained at the Hanford Engineering Development Labo

ratory, and on other combustion techniques being developed at various s i t e s . Judging fross t h i s tour, i t

was held that acid d igest ion would be the most

suitable process for the treatment of E«iro-

chemic's plutonium-bearing combustible wastes.

>. f-;i;. >••: fde iil)Jt,i|..t,<i,ii i'j Maritim MiA

f ia l i ' i i im bit i*f1.<Cf,<C'il Cill-cmiltüjj'aplitj

.<> >i ",'ai.l ("i l i tcvi ' l i i c i ulaiuimi and ;:iu-

(cuivi |Vn; iitifltyNciU' iiijfUt'cul uxtitii.

r •; ; <.:?,<•;, liunt'4 JH i'vy.-.i'n'UJ c( flu'

.! S S, ;),!'< [I) t i V V ; fMCfi i t , ' liu'lCJ (kt.l.U l!<

' . ' ! ( ( »:.' . < . ' ; l»,' if .

SI

Ih« Acid d igest ion process consists ut the following three s t eps :

* ' > Eï£ï-£E5ÎÇI*Î965FÎ

A conceptual design has been made of a glove-bos chain allowing the required operations of emptying

the sol id-waste containing drums, segregating the non-combustible and combustible v a s t e s , shredding

the U t t e r and repacking both types . The shredder has already been ordered, and in the swan t in»

detai led drawings of the ins ta l la t ions are being node.

(2) çamusTips bit ACID.DICESTion

fcichiu the frame of an agreement between Eurecmemic and Cfl (Karaforschungszentrum, Karlsruhe), the

latter has been dealing with th i s step in the process . The glove boxes to be ins ta l led at Eurochemic

nave been constructed. Meanwhile, acid d iges t ion using a mixture of sulphuric and n i t r i c acid has

further been cold tested during 1977. These t e s t s w i l l be continued during 1471.

(3) lECOVOtT OF PUiTOmUH taOB ACIP-OICfcStlOS KESIDBES

Research and development work on the recovery of plutonium from ac id-digest ion residues has been

concentrated on the application of extract ion chromatography using tributylpRosphate (TIP) as an ex-

tractant .

Break-throttgh curves have been recorded for different concentrations of plutonium, at varying concen

trations of sulphuric acid and n i t r i c ac id; te la t ter being chosen as a solvent of the ac id-

digescion residues.

It proved that sulphate ions in concentrations of ^ 0.2 H ser ious ly interfere with the plutonium-

loading of the extraction columns. Heans to overcome the interference by pretreating the feed solut ion

are s t i l l being examined.

Eurochemic w i l l continue to do experimental work on actual ac id-d iges t ion residues produced from

standard and/or real plutonium-bearing so l id wastes.

LIBRARY AND PUBLICATIONS

53

During 1977» the a c t i v i t i e s of the Library and ikvmnentation Services have remarkably increased. A

large nuzler of l i terature search requests were tceated, partly with the help of the ISIS (Internat io

nal Nuclear Information System) imputer terminal of the CEN/SCK. The number of l i terature requests

sent to other l ibraries or indiv iduals , on the other hand, have decreased by about I5Z, as compared

to 1976. Over a hundred requests from other l ibrar ie s and individuals were received during 1977.

The c o l l e c t i o n of the library has been enlarged by over SOQ i t e a s . These can be broken dovn as follows:

BOOKS

F u l l - s i z e r e p o r t s

M i c r o f i c h e r e p o r t s

p a t e n t s

S p e c i f i c a t iens

R e p r i n t s

r.EW i Tens

1976

56

5C

208

5

10

11

1S77

ae

58

247

17

38

57

DIFFERENCE IN 4

• 30

3

• 14

• 240

• 280

• 417

The documentation services edited several internal documents and preprints for symposia, conferences,

e t c . . . (see nest chapter). These documents w i l l not be published as ETR's, since oost of these papers

are , or wi l l be printed in the proceedings of these meetings.

During 1777, one Eurochemic Technical Report was issued:

ETR-293 ACTIVITY REPORT 1976, by W. Drent (Ed.) and E. Delande.

(Cat. IV, publicly ava i lab le ) .

Several ETR's were being prepared and wi l l be published in the course of 1978.

Eurocneciic staff members published the following papers in the nuclear f i e l d :

— Several contributions to the NKA report "OBJECTIVES, CONCEPTS, AND STRATEGIES FOR THE

HASACKKEKT OF RADIOACTIVE WASTE ARIS1NC FROM NUCLEAR POWER PROCRAMfES ' NEA OECD, September,

1977, were submitted by H. Eschrich.

— "SURFACE DECONTAMINATION" by H. Eschrich, 20th chapter of "Chemie der nuklcarcn Entlorgung",

Thiemig Taachenbuch, Sand 66/1 , Karl Thiemig Verlag, Hun.hen.

— "STORAGE AND SOLIDIFICATION OF LIQUID HIGH-LEVEL WASTES" by H. Eschrich, to be published

in "Chemie der nuklearen Entsorgung", Thiemig Taschenbuch, Band 66/11, Karl Thiemig Verlag,

München.

— "TECHNIQUES FOR THE SOLIDIFICATION PF HIGH-LEVEL WASTES", co-authored by J . van Ceel,

Technical Reports Scries no. 176, IAEA, Vienna, 1977.

CONFERENCES AND SYMPOSIA

55

During 1977, Mr. A. Osipenco has been acting as chairman of the Belgian Association for Radiation

Protection. He had been elected a^ chairman during the General Assembly of th i s Association in December,

1976; the duration of Mr. Osipercu's mandate as chairman i s two years.

During 1977, Mr. J. Alderhout attended the meetings of the Dutch Society for Radiation Hygiene.

Mr. F. De Blander participated in a tour for exploration and inquiry in the United S ta te s . Together

with representatives from Nukem and GfK, he v i s i ted various Erda ins ta l la t ions for the treatment of

combustible so l id plutoniusi-containing wastes. These v i s i t s took place between February 26, and

March 19, 1977.

Mr. J. van Geel participated in the IAEA Advisory Group Meeting of Experts on the "Techniques for the

So l id i f i ca t ion of High-level Wastes", . t Karlsruhe, February 28-March 4, 1977.

Mr. H. Eschrich participated in the seminar on the "Chemistry of Nuclear Fuel Reprocessing ant Waste

Management", organired by the Society of German Chemiits, section Nuclear Chemistry, at Cerlos, March 7-11 ,

1977. Mr. Eschrich presented two papers: "Storage and So l id i f i cat ion of Liquid Radioactive Wastes" and

"Surface Decontamination".

Mr. E. Det i l leux gave a lecture at the "Institut Supérieur de L'Etat pour les Sciences Nucléaires

Appliquées (ISNA)" - the Higher State School for Applied Nuclear Sciences, at Brussels , March 11, 1977,

on the question "Les déchets r a d i o a c t i f s , s o n t - i l s un obstacle technique à l ' u t i l i s a t i o n de l 'énergie

nucléaire ?" - Do radioactive wastes const i tute a technical obstacle to the use of nuclear energy ?

Mr. J. Alderhout attended the 4th International Congress of the International Radiation Protection

Association on "Radiation Protection: An Example of Action against Modern Hazards", at Par i s , France,

April 24-30, 1977.

Messrs E. Deti l leux and J. van Geel participated in the International Conference on Nuclear Power

and i t s Fuel Cycle, at Salzburg, Austria, May 2-13, 1977. Mr. Detil leux presented the following paper:

"Criteria, Standards and Pol ic ies Regarding Decommissioning of Nuclear F a c i l i t i e s " .

On May 24, 1977, Mr. H. Eschrich presented "The R t D Programne on the Management of Radioactive Wastes

at Eurochemic", at the AB Atomenergi, Studsvik, Sweden.

Mr. E. Deti l leux participated in the Annual Meeting of the Belgian Section of the American Nuclear

Society at the SCK/CEN (Belgian Nuclear Research Centre), Mol, June 8, 1977. Mr. Deti l leux presented

the paper: "Is the Reprocessing of Spent Fuel a Technically Reliable Industry and a Just i f ied Act iv i ty

for Belgium ?".

Mr. F. De Blander participated in the Conference on Lead and Zinc Technology, organized by the BHT

Metals Technology Centre of Wantage, Oxfordshire, in London, England, June 14-15, 1977.

Mr. J. van Geel participated in the First Research Coordination Meeting on the Evaluation of Sol id i f ied

High-level Waste Products, at Battel 1c Pacific Northwest Libs, Richland, LSA, June 20-24, 1977.

56

Kr. H. Etchrich f ave the nain lecture at tac 17th General Meeting of the Society of 'e:=-!n Chemists,

at Munich. September 12-16. 1977. on the "Sol idi f icat ion of highly Active Vastes".

Mr. J. van Ceel participated in the seminar on the "High-level Waste Product Characterisation" at

Richland. ISA. October 4-18, 1977. Mr. van Geel presented a paper on "Development Work on KLV S o l i d i f i

cation at Eurochemic".

Mr. R. Swansea participated in the Advisory Group Meeting on PAFEX I and PAFEX I I , organixed b" the

IAEA, at Vienna, November 16-18, 1977. Mr. Svennen presented a paper on "The Preparation of a Diluted

Input Solution for PAFEX II / Input Accountability Procedures at Eurocbemic".

Mr. A. Osipenco vas a member of the programme committee of the Seminar on Radioactive Effluents from

Nuclear Fuel Reprocessing Plants , organized by the CEC, at Karlsruhe, FR Germany, November 22-25, 1977.

Mr. Osipenco presented a paper on the "Operational Experience of Caseous Effluent Treatment at the

Eurochemic Reprocessing Plant".

Rr. A. Osipenco attended the meetings of Che NEA Committee on Radiation Protection and Public Health,

at Paris , France, as an observer.

Mr. A. Osipenco participated in a working group on "The Safety of the Fuel Cycle", set up by the

NEA Committee on the Safety of the Nuclear Ins ta l la t ions , at Paris , France.

APPENDIX

iJtNMAL AU^NELV

1. 1 List of Shareholders in the Company, on December 31 , 1977

57

Avv'ù'ûlïV-x

ïte: G o j b r n r - ü n t cj t . V " Ö Ü U M M J . R ö p u L I i c ü f ü tó rnuny

^ h u i ^ i S w ^ - W e s i ^ f ï i i û i i i e a L l t i t . t r L J i i t S t s w e r f c tRV*E), t s s e r .

A r t ? i t S[M;rn-.> i n s n u i f t . ! . . L ' j ' : ; : ! . t r L n c r g i e j c r r ^ r t - j r : r ; s -

u n t - . : ' ' ; u h - i - . ; z ^ r .<• . j i ' t - • : : ^ . . . r r . j ^ r Lr r i - h t j - ' v ; ' J I M Ü L I

L e i r . t ' j n g s - V s r ö J - P . . . - • •••'„-.rr, <•;.'.'; G-v/G} , L " :.;.->& h i n r f

L j r c s r . k r a f t i- .or K '1 •»- ' - N ; 1". ^G , n ^ n h t i r i - G t ^ k a r a u

S r . t ; i n K D h l y n - r : ; 6 K t r i z i t ; J t r ü i V - L ü g ) , f-.sscn

E laJenwerK A G , c d r i ^r . , . ; ; '

t l â r ; . L L i r e i s - b t - : I c i - *..: i," i*":>tr, i . ' .arf L- A G , Lüru;_j:-£

! " • • , . - ? i s z h e ü l p f * : r i - ; t - ü t r —P f P r G i i r . L ^ r ' j I r - t r j ' .

h ^ n e v e r

A l l r i - . b i n e t l e k t r J ^ i l S t s - C e s u l l s c h a f t (AGGj ,

F r . j r ' r f . i V t / i - ' . - i l n

I n t e r a t ' j n * be.n : ; , . . . - , • b . r-.Gin

GuKem Gmbh, k j ! ^ ; . ' r v

M E t d l i - G f j S b i l G L f . i f t AG. r - r a n K f ' i r t / H a i r ,

' i / ü r t d n i g t e L I f c K t r L z i t ü t o w t i r M ï tastfalen A G , G o r t n u n a

Bi ovvn CiovE-ri â G Î F . AG, f"J i n r t . ^ i n

F ' d iTKGrke n c e i ' i s t AG, ' - r ^ h - ^ r t / ^ i r - r ^ L - h s t

i- c i r ' - L ^ ^ a ^ r i"X''.< l\\ jVA A G , « i : ; K r K . j : i ^ '

Tfie ' • ' j vc r ' ! f : i t -T ' t u f * : > : '•'^,..\.v,l j.„• o f ' H / = t r i d

T V ; i.cvi. jrf: r ,. ' i jr '• '-t ' tM- t I : , • " ,n r,f H - ^ . i ^ r - :

• J ^ : ! - T i i i G>. - ; . - I i " ' L ' • : : • ; : i I:K:> L I ' " i ' i ' . i u t iü r j t

I f •; r ^ r - i c l i t : - . . : 1 • - • ; - r ; i . >. 1 !

: j n c i - ; f , G G P T r n ' : M r > r t.'. " l. G - t r i c I t.G

T f i u u:j ' . '* jrnrT.r t or' '_!• r ; • , • Gi"; -. : : t ' ' ' -n, ; rk

J j n t - j Js; ; T:-:r rT Gi '*• . ' - > * r , .r1 : ; ( r i •:

- ~ r r i ^ i -J : i.'t- ' j J ' " .'..t ;' '•> ••'.';••.; -:.JK'. , i" . jr i r :

G !.T-i'jtfc' GGr • r G> *".. J : j f ' "• J ' T ' i i i ' . G Gr , i , ^» , i i ( ;. : ' jGG i ,

'-0 , ; : . ( - . ; ' - U , f' : y ; t;

G'jf-, 1:jf.L '»jî:,'fi.jitj r..,p.r i ' Lns rp i j Y-dcar!.., r:-...'

• ' s ' - i ' ] • ' ' ' " ' , ' ' t ' • ; • ] ' • ' G * ' ' i ' , ' ; i - •. ' • .-

' : c - : ! t . ' t t i r i r . - . ; r .G-j I"E i . " * 1 • • u - l b ^ r i i ' G G T . i , H ' . ^ r -

T' r. G ' ^ - L T ' i ' i ^ ^ t - , t *G , ' ! r v :r<r o f Y . r / , - . i ,

' , '. '...: , ' L' <.T , G: : • J ' , G •: , : . ' i i

;< L . . - • • ' • • . ' • • . ; - , ! • • r . : . : G

fiUriOLR OF

5G .0C0

EMA l j / A

110

1

1

1

1

1

1

1

1

Z

2

:<c

7 f j

13

14

37

1RR

17

k'b

B

;'-'

SHARES

2 ' i , r

CMA

OF

!'Q

U/A

1

1

1

1

1

TOTA^ tMA L/A ( * !

5 , 5 : 5 , CCt:

sn.ccu

5 0 . L C J

sr./.iGi

so,oca

5 0 . G C C

5 C . C C C

5C,reu

5 0 . C Ü L

5r,,ncp

5 2 , : i C i

îc.cr.i.

•M, :::[,

sü.rc'i

5 C . '-•':

1 o r , •:;.:.

nr'.ici', 1 , 5 0 L , . j r , ;

3,75'J, ' . ;Uf. '

C ' ; r i , ' ] : 'P

7 i ) i . , . ' i :

1 ,1s.': .rr.:

;•,*•:•'.<,'"•'

L.,1.y , l j : ' ' l '

1,10':,.; ' . '<. '

1 , 6 5 0 , : / / ' .

1 0 0 , L'O;0

; ' J O , C O O

1 , 4 ^ i , , " . '

3Ü! , ' I / .

z , / 0 f ' , r " . .

& ! , • . ' , • ; : . ! .

1 . 2 L i s t o f B é n é f i c i a i ^ Shareholders in the Company, on December 3 1 , 1977

-r-^r-tr-ÜLLtr-E

Thfc Government cf the f e d e r a l Repubi ic nf Germany

'rife Government uf t ne Repub l i c of A u s t r i a

Trie Government c f the Kingdom cf r js lgium

Trie Government of the Kingdom of Dp.r.mctr^

Junta ce t n e r g i a Nuc lea r , Madrid

Commissariat à l 'ÈLnergie Atomique. F a r i s

Gumitatu : tóz iona ie per l ' G n e r g i a Nuc leare , Rome

The Government o f the Kingdorr. of Norway

Junta 'Je Energia Nuc lea r , L isbon

« l - t i ebo iage t A t o n e n e r g i , Gtockholm

^•e Government of the Swiss Gunfer icrat ion

The- Govt rnment of the T u r k i s h Republ ic

TOTAL

TCTAL iXr.THIBUIiat ; ON G'fX. 31 . 1077 LÎ1A U/A ! * )

20.442,715

1.6Q7.2b3

3.406.527

1.955.528

2.672.077

17.1G5.5Q2

3.693,506

1.401,30b

324,6D1

3.954.334

3 ,022.861

20.325

59,606,535

MiniiL* Gh faLr.jiFiG :,••;• Y ShAHES U * J

4,086

321

5B1

3S1

534

3,421

733

260

54

79C

504

4

11.915

i l ' 1 E » Ü/A - 50 B e l g i a n f r a n c s .

! *« ) une share i = a t t r i b u t e d ' o r each f u l l caymcnt o f 5,000 GriA G7A.

BOARD OF DIRECTORS

IREÇTQRS

A l b o n e t t i

B a s t r u p - B i r k

C a r r e i r a - P i c h

T r e r o t t e

Gu t i e r r ez - . ] ud:

L e f è v r t

R, i l a r i c q

A. N((jd

P e r r c t

M. P i : t e t

r. Pandl

Gchiitt

Gteinwundur

G. Ts;r G.uen

ALir^NATEG

f) . Z i f f e r f i r o

F . Gejcn^he

L. uopez-F^:

Î . l a m e l l e p . Lou is

G. r j i l son

H, iJüussard

G. i lu sy l

G. G. M.mo'Jt,

GUr-tTAJ-Y

TECHNICAL COMMITTEE

>. S o i - s s e l i t r

fttMSEF.5

n . B i l d s t e i n

I . d ' hon t

•*. Hu l tg ren

B. Lopez-Perez

S. QrlOKsKy

R.P. Randl

K. S inger

S.G. Te r jesen

H.R. von Gunten

PI. Z I f f e r e r a

AUDITORS

14, fJecKer

L. Flamand

J . Gansmandel

MANAGEMENT

f-. Qs t i l ieux

LLPUTY HANAGErV

H. Eschr i ch

TRAOE UKIOH OEUftMlON

Alonso fluncw

tier*

Do Eie

Lope/ Jo Mor'.

w i l . t i r ' .

ALTf.PNATf.rj

Ue Valk

PHlr m

y . jn u t » . I

Vr.jr: ', t i r

http://ALTf.PNATf.rj

WORKS COUNCIL

Regreeencativei of the Manageaent

CHAIRMAN: E. U e t l l l e u x

VICE-CHAIRMAN: H. Eschrlch

Representa t ive» of the Personnel

MEMBERS:

ALTERNATES:

J. Cools

M. Demonie

0. Martinelle

J. van Geel

M. Balseyro-Castro

W. Drent

N. Frankignoul

L. Geens

Y. Marchant

R. Swennen

SECRETARY:

MEMBERS-.

ALTERNATES:

J.

P.

A.

n. G.

r,.

E.

J.

L.

P.

a. «..

Alaerhout

Ber*

De Ble

Oe ValK

Van Neer-Horemans

Vermeulen

Burny

Caers

Humblet

KoKkelenbbrg

van Dael

Wessellng

COMMITTEE OF SAFETY. HEALTH. AND EMBELLISHMENT OF THE PLACE OF WORK

R#/pre»entativ«e of the Management

CHAIRMAN: E . Det i l l eax

SECRETARY: A. Dsipenco

MEMBERS: J . Cools

M. üemonie

N. Franklgnoui

J. «an Geel

ALTERNATES: H. Eicfirion

J . Aldarhout

M. 8el»«yro-Ca«tro

F. B i r t e lB

L. Gaan»

0 . M a r t i n e l l e

^ÏELîiîulîtiïîi_°i_U!£_EîIÏ£SSîI

MEMBERS:

ALTERNATES:

E.

A.

D.

R.

G.

K..

W.

J.

L.

L.

J.

A.

Burny

Se Bie

Geboers

Huygaerts

Vermeulen

WaiMllng

Bolle

Caere

Kumolet

Hartens

Palmen

Ruts

Date post:	17-Feb-2022
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ACTIVITY REPORT 1977

Documents