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Waste Management (spent HTR-fuel elements)

Kurt Kugeler Institut fur Sicherheitsforschung und Reaktortechnik (ISR)

Forschungszentrum JMlich Institute for Safety Research and Reactor Technology (ISR)

Research Centre Jilich

July 25, 2001

on the occasion of the visit of the NRC-Delegation to Germany on the Topic Safety Aspects of HTR Technology (GRS Cologne/FZJ J0lich) July 23 to July 26, 2001

I

C.-,.,0". 0 f cx,- K,

overview:

reactor I

TFuel < 100 °C

TFuel < 50 oC

0

time 3 years

time 50...100 years

time 105 years

long storage time (.400 years) optimal for intermediate storage

* ceramic fuel elements resistant in final storage

intermediate storage

LI

Storage of spent HTR-fuel elements

RN

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32

Abb. 3.11: Zeitliche VerhAufe der Nac hwýrmeproduktion bei verschiedenen HM-Konzepten mit kagelfo- rmigen Bre=elementen

lam Ma wo 7M Ma sw

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so M TL M 6

la

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Abb. 3.12: Zeitliche VerlAufe,ýer Nachwarme und der Tempem= des heiBesten Brenn

stabes fur LWR-Brennelemente (CASTOR-IB, 4 DWR-BE, max 25 kW, 2 t Uran

Toxicity Potential I SvIGW&.1

+n I

CC

3

I -b m + 0

Intermediate storage of spent HTR-fuel elements

concept:

a irn ---

ALt

1'

A 'I

I'

I'

--> aiir out

storagee building (1,3 m concrete)

.cast iron vessel (withi internal ca nnisters from austenitic steel)

d. conclusions:

* fuel temperatures below 200 'C

0 system protected against outer impact

0 there are no accidents caused by internal or external reasons, which result in non- aflowable rekease of fission products (.,catastrophe-free nuclear technology")

*i storage time of 50 to 100 years optimal releated to total costs of spent fuel storage

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lDberwachungseinrichttmgen mim Merprdfen der Doppeldeckel sowie Eiuricbtungen zur

Umgebungsdberwwhang sind wie fiblich vorhanden.

Ein hinreichend groBes FreigelAnde umgibt die LagerhaUe und gewdhrlelaet dea ablichen

Zugangsscbi= und tV daza beý daB die Dosisleistimg am Anlagenzmln unterhalb vorge

schriebener Werte gehalten werden kann (D < 10 tiSv/h).

Zildhaffig evtL noch niedrigere Werte kOnnen durch verstArlae Abschhmumg oder ein gr6Be

res ClebaWe realisiert werden.

Bremelement: R nsrý ý:

Part&eltyp: SchwermetaUgehak: Anfangsameicherung: mittl.,Abbrm2&

Realdor: tam Laisttmg: mittlere Leistmpdicbte: Lastfidaw. jihr.L BE-Meage:

LEU TRLSO 7 g SM/BE 9 % so 000 mwd/tsm

200 MW 3 MWhxP

O's 105 000 BE/a

Zwischenlagerbehilter-. H6he: 6 m bnenduramemer. 1,6 m Wandstirke: 0,4 m Gewicht 113 t Werkstom SphiroguB

i 2 Decked -n3k Dkhtimgcn

b)a)IrI

Abb. 3. 1: Zwischenlagerung abgebrannter Brennelemente beim MODUL-HTR von RiTERATONVSIEMENS a) Zwischen4erbehi4er b) Daten von Brennele.menten und ZwischenlagerbebAlter

Final storage of spent HTR - fuel elements

coiicept:

I*"m

steel vessel

-//////.///,,--a/.o

coi'eequences: % Wul temperatures below 100 0C.

* sakt ltmperatures not changed

* no accidents from internal or external reasons which release non-allowable quantities of radioactivity to the environment (water ingress MON requires some investigation)

• ater10 5 years the radiotoxicity is in the

same order as that of fresh fuel

U-

A

VI

light weight drum with backfill option

pressure resistant cast-iron containfer'

Abb. 4.2: 400 I-FaBsysteme zur Endflagerung abgebrannter HTR-Brennelemente a) 400 Liter-Fal3; b) Guj~container b) druckfester GroBcontainer

IVolumen des F asses 400 Liter

Zahi der Brennelemen- 1.800

te/FaB

FaBh~Aic 11 cm

FaBdurcbmesser 78 cm

Fafgewicht

tAtvttF aIWdrme/FaB3 -

- 500 kg

< 50 W

6.10 12 ]Bq

Tab. 4. 1: Daten eines Abfallgebindes fu~r abgebrannte HTR-Brennelemente (Beispiel: StAhlgul)

76

S

E 40

78 cin

A

A

final storage of burned fuel elements

coated ):'i SiCC particle. 0 +P0

matrix UO2 +PuO2

fuel element

steel vessel layers of earth

fuel elements

coated particle

Il

* release of radioactive material from the final storage can happen just after a very long time

* the amownts of radioactive material are relatively small

* only very small higher doses than the normal doses can be caused on the surface of earth even after extreme accidents inside the final storage system

Final storage of radioactive waste

Results of leaching experiments on HTR - fuel elements

"I 4

'2 �*1

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105

102

101100 300 500 700

Relaeserate of Cs 137 to alka•me solurium

Bq / days

9"

days

CD

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0

I0

Pm")

,4EC13

..... ...d

U) CD a;C

0 0

- 0 0 0

-~ 0 L. a

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0 0S

-. X

cc U) 0c

U,

Final storage of high level radioactive waste

Yearly individual doses from final storage

of glass containers in granite

time after closure of final storage (years)

Reference case (glas blocks storaged in granite)

Accident assumption: water flow is higher by a factor of 100

zN

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S 0

>1

Innovatives Konzept zur Endlagerung abgebrannter Kembrennstoffe

voneinander unabhan'rgige Barrieren

1. coated particle

TRiSO- oder B ISOcoated particle

3. SiC-Container

2. B re nnelemerbmt breiwisto~elfei Grapit.-Matnix

Bre anastelizone mit coated particles

4. StahlbehMileur

Brenn--element

N\Fugezone

,SiC-Behal~ter

SiSIC

5. Geologische Barriere,

U~niv.- Prof. Dr.- Ing. K. Kugeler

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11W M, AAC"M

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IC Radiotoxicity of waste: direct final storage of spent fuel

elements compared to partitioning and transmutation

1 E+I -1----------• D -U•-Cyc l ~35 GWd~t SM

-~ 1E+09 -..

I1 E+08 - I"Actinides

S". (direct final "•I ° storage)

C 14 1 1E+07 - .Act•e "W . Actinides (today WMA 0 0. % (after P&T)I

1 E+0I

0

O1E+05- -. 4

fuel N

I1E+04 I0 .I 1 102 163 104 165 1'6 10)7

time I years

* direct final storage of burned fuel elements

-- proof of safety of storage for 106 years

* partitioning and transmutation

-4 proof of safety of storage for 1000 years

Plutonium - ways of further handling

Comparison of disposition options to consume and degrade weapons plutonium (after General Atomics)

Weapons Plutonium

Vitrification Spent fuel Deep burn option option option

(LWR - Mox) (MHR)

RAPD option

(MHR -Accel)

(0

O.6

4)

E

0

0

100

90

80

70

60

50

40

30

20

10

0