FUTURE NUCLEAR FUEL CYCLES: GUIDELINES… 1 … · Nuclear fuel cycle in Fran ce ... depleted...

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Bernard Boullis – SFEN-JG, november 2011Nuclear fuel cycle in France – Status & prospects

FUTURE NUCLEAR FUEL CYCLES:GUIDELINES…

Bernard BOULLIS,

CEA, Nuclear Energy Division

Program Director, Nuclear Fuel Cycle Back-end

ATOMS FOR FUTURE – PARIS, 8-9 november, 2011


FUTURE NUCLEAR FUEL CYCLES:GUIDELINES…

ATOMS FOR FUTURE – PARIS, 8-9 november, 2011

1- The current french nuclear fuel cycle2 - Towards sustainable nuclear systems3 - Drivers for R&D

2


Fuel fabrication

Uranium enrichment

Mining and milling

RECYCLING

WASTEFPs and

MAs

40 t

used UOX 1000 t

(UOX 1000t)

(MOX 100t)

Plutonium #10t

Uranium (RU) #950 t

used MOX #100t

Uranium Conversion

depleted RU

800t

depleted uranium 7000t

used REU #150t

LWRs

THE PRINCIPLE OF THE FRENCH CLOSED FUEL CYCLE

(approximative amounts/year)

(REU 150t)

natural U8000 t


FINAL WASTE VITRIFICATION

180 liters

#15% FPs

# 10-15 glass canisters /reactor /per year

3


GLASS CANISTERS DISPOSAL

1mSv/y

1μSv/y

DOSE AT FINAL OUTLET100 000 y 1 M y

(ANDRA, « CLAY REPORT », 2005)

#1 µm/50d , early stages

#1 µm/1000 years, steady state


CURRENT RECYCLING STRATEGY : THE RATIONALE

- saving uranium resources(#10% of French nuclear electricity from MOX fuels);- mastering the growth of plutonium inventory(Pu flux adequacy : Pu from processing= Pu refueled)- safe & secure ultimate waste without plutonium;- the plutonium available for future use is concentrated in MOX spent fuels (7 UOX -> 1 MOX)

- an already large industrial experience , operated under international safeguards

( #25 000 tons reprocessed, # 2000 tons MOX)- suitable option for Generation III reactors

4


LONG TERM SUSTAINABLE NUCLEAR SYSTEMS

- efficient burning of plutonium,- full use of uranium,- potentialities for improving waste management ,- no enrichment needs

- initially fueled with plutoniumcoming from spent MOX

- breeding gain could be adjusted in the future(according to energy needs)- able to recycle more -in a later step -(transmutation of “minor actinides”… )

(1) RECYCLE, (2) IN FAST REACTORS…

A progressive deployment?

0.000.100.20

0.300.400.500.600.70

0.800.901.00

U235

U238

Np23

7

Pu23

8

Pu23

9

Pu24

0

Pu24

1

Pu24

2

Am24

1

Am24

3

Cm24

4

Fis

sion/A

bso

rpt

PWR

SFR

Robert N. HillArgonne National Laboratory

233rd ACS National Meeting – Chicago,, 2007


coal, 400Gtoe

Uranium40 Gtoe

Gas150 Gtoe

oil165 Gtoe

Uranium, 4000 Gtoe

Uranium use in thermal neutrons reactors

Identified conventionnal resources, Gtoe(mémento sur l’énergie,CEA, 2010)(Pétrole 165 Gt, charbon 826Gt, gaz 180 Tm3,uranium 3,3Mt)

FOSSILE FUELS POTENTIAL RESERVES

Uranium use in fast neutrons reactors

5


Estimated dose, Saulx, spent fuel(Andra, rapport argile, 2005)

SPENT FUEL TOXICITY

1E+1

1E+2

1E+3

1E+4

1E+5

1E+6

1E+7

1E+8

1E+9

1E+10

10 100 1000 10000 100000 10000

Temps (années)

Inve

nta

ire

rad

ioto

xiq

ue

(Sv/

TW

he)

Total combustible

Plutonium

Uranium

Actinides mineurs

Produits de fission

1010

109

108

107

106

105

104

103

102

10

Main contributors to intrinsic toxicity

Pu>MAs>>>FPs


FUEL FABRICATION RECYCLING

WASTEFPs

(MAs)(40t)

Plutonium (#20%)depleted uranium

(40t)

FRs

Uranium (#80%)

MOX-FR450t

used MOX-FR450t

(minor actinides (# 5t))

ACTINIDE MULTI-RECYCLE IN A FR FLEET( principle values, self-balanced fleet, 400 TWh/y)

6


LONG TERM SUSTAINABLE NUCLEAR SYSTEMS

- efficient burning of plutonium,- full use of uranium,- potentialities for improving waste management ,- no enrichment needs

- initially fueled with plutoniumcoming from spent MOX

- FR/LWR deployment could be adjusted in the future(according to energy needs)

- able to recycle more -in a later step -(transmutation of “minor actinides”… )

FAST REACTORS, THE BEST ANSWER…

A progressive deployment?

RECYCLE, IN FAST NEUTRON REACTORS…


Generation 3+

Generation 4Existing fleet

40-year plant life

Plant life extension beyond 40 years

0

10000

20000

30000

40000

50000

60000

70000

19

75

19

80

19

85

19

90

19

95

20

00

20

05

20

10

20

15

20

20

20

25

20

30

20

35

20

40

20

45

20

50

20

55

20

60

Average plant life : 48 years

Inst

alle

d c

apac

ity

(MW

e)

60 000

Fast reactor Prototype

?

FROM LWRs TO FRs…A SCHEMATIC PATHWAY

??

7


TOWARDS SUSTAINABLE NUCLEAR SYSTEMS

-reactors?

- fuel cycle technologies?

- deployment dynamics (strategy)?


FAST REACTORS DEVELOPMENT : FRENCH STRATEGY

- Sodium Fast Reactor, the reference option : ASTRID, the prototype

- maturity, possible further improvments(safety, operability, economics)

- commercial level 2040

- developped with industrialand international partners

- Gas-cooled Fast Reactor, a long-term option:( ALLEGRO, experimental-scale project)

- attractive potentialitiesbut heavy challenges(materials, fuel, safety)

- in Europe?

8


THE ASTRID FAST REACTOR PROTOTYPE

sodium-cooledpool typeoxide fuel#600 Mwe

« Advanced Sodium-cooled TechnologicalReactor for Industrial Demonstration »



-reactors?



9


RECYCLING TECHNOLOGIES

• FUEL: (MIXED) OXIDE( far future: carbide, metal…?)

• PROCESSING SNF: HYDRO-PROCESSES[reliability, high yields, low waste amount]

• FUEL MANUFACTURING: POWDERS BLENDING

Procédé COCA*

UO2PuO2

Dosage

Broyage et tamisage

Pastillage

( étape granulation

éventuelle)

Frittage

(U,Pu)O2

rebuts

lubrifiant

Broyage

rebuts

Rebuts


RECYCLING TECHNOLOGIES : DECADES R&D!

U, Pu, FPs,MAssolution

HULLS

SPENT FUEL HNO3

TBP

FPs, MAs

U

Pu

DISSOLUTION EXTRACTION

high yields…

…technological waste low amounts

10


CADARACHE

MELOX

0

500

1000

1500

2000

1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008

(tHM)

La Hague plant (tons/year)

MOX fuel fabrication(cumulative tons)

SPENT FUEL RECYCLING IN FRANCE


1-ADAPTATION

(HBU, MOX fuels,…

…FR fuels!…)

RECYCLING: GUIDELINES FOR R&D…

11


FAST REACTOR OXIDE FUELS

many differences FR fuels / LWR fuels

Fuel sub-assembly, structure elements

Higher In-core temperature

Higher Pu content

Higher burn-up

Fission products resp. yields


FAST REACTORS OXIDE FUELS FABRICATION

Procédé COCA*

UO2PuO2

Dosage

Broyage et tamisage

Pastillage

( étape granulation

éventuelle)

Frittage

(U,Pu)O2

rebuts

lubrifiant

Phénix

SuperPhénix

AtPu(Cadarache)

12


PROCESSING FR FUELS

• Fuel dissolution(dismantling, dissolving)

• U-Pu (AM)- /PF separations(performance required?)

• liquid to solid conversion (high Pu flux)

• Structure elements management(nature , amount, radioactivity

• FPs vitrification(platinoids)

• Criticality risk management(specific design)

Process adaptation needed…


Pu RECYCLE IN PHÉNIX

1973 : start of operation

1980 : 1er sub-assembly loadedwith recycled Pu

520 sub-assemblies processed, 4,4 t Pu recycled

0

100

200

300

400

500

600

700

800

900

1000

1100

1200

1973

1975

1977

1979

1981

1983

1985

1987

1989

1991

1993

1995

1997

1999

2001

2003

2005

2007

2009

Année

Nombre d'assemblages

FabriquésChargés en cœurDéchargés du cœurDémantelésRetraités à MarcouleTotal retraités

13


1-ADAPTATION(innovative fuels)

2-IMPROVEMENTS(a « sustainable goal »…)

COEX



• no pure plutonium

• a solid solution (U,Pu)O2

THE COEX CONCEPT

COCA fuel COCA-COEX fuel

R TU

U- Pu

PF

U

14


VITRIFICATION: THE COLD CRUCIBLE TECHNOLOGY

• Cooled wall, direct induction heating

• Corrosion issues drastically decreased

• Higher temperature, higher reactivity

hot wall vitrification process

Waste stream

Hot wall crucible

Glass frit

Calciner

Glass canister

Waste streamGlass frit

Calciner

CCIM

Glass canister

CCIM vitrification process

in operation at La Hague , 2010




3-EXPLORATION P&T (minor actinide recycle)


15


MINOR ACTINIDE IN SPENT FUEL

UOX MOX-REP

MOX-RNR

237 Np 1.67 0.47 0.29

241 Am 1.11 9.6 2.75243 Am 0.44 5.4 0.81

244 Cm 0.14 2.3 0.33245 Cm 0.01 0.30 0.027

[en kg/TWhe]


MINOR ACTINIDE RECYCLING :WHAT ARE THE DRIVERS ?

0,1

1

10

100

1000

10000

10 100 1000 10000 100000 1000000

Temps (années)

Rad

ioto

xici

té r

elat

ive

FINAL WASTE RADIOTOXICITY REPOSITORY « FOOTPRINT »

With

ou

t transm

utatio

n-120y

MA

transm

utatio

n-120y

SNF direct disposal

Current glasses

MA transmutation

U ore

Minor actinide transmutatation may provide :-a drastic decrease of long term radiotoxicity of final waste-a significant decrease of the repository footprint

MA : Am, Cm, Np

16


THE 2006 FRENCH ACT(RW & nuclear materials management)

PRINCIPLES :

– RECYCLE (reprocess)to decrease waste amount & toxicity

– RETRIEVABLE GEOLOGICAL REPOSITORY,

for ultimate waste

A « ROADMAP » :

–2012 : assess the industrial potentialities of advanced recycling options (prototype 2020)

–2015 : repository defined (operation by 2025)

28, june, 2006


MA PARTITIONING

P

O

O HO

O

DIAMEX /SANEX

U UPu Am (and Cm)

FPs.SNF

PUREX /COEX

NCH 3

C 8 H 1 7

CH

NC H 3

C 8 H 1 7

O O

C 2 H 4

OC 6 H 1 3

N

O

O

O

N

OH

OH

OH

OHHEDTA

N

O

O

O

N

OH

OH

OH

OHHEDTA

DMDOHEMA

HDEHP

innovative partitioning processes developped by CEAbased on the design of new extractants

MA recovery processes have been successfully experimented,(kgs -sale , genuine spent fuel )

17


MA RECYCLING OPTIONS

20-24

21-23

19-23

18-20

19-17 23-21

23-17

21-17

17-16 22-2120-1918-17

19-22

19-2017-18

17-20

22-1920-17

18-1816-16 21-21

21-19

20-22

21-20

20-23

20-21

18-21

23-18

23-2021-18

19-1917-17 22-22

19-21

22-18

22-2020-18

18-1916-17

17-23

17-22

18-22

17-19

16-20

16-21

16-22

16-23

16-24

17-24

18-24

19-24

20-16

21-16

22-16

23-16

24-16

24-17

24-18

24-19

24-20

15-16

14-17

13-18

12-19

11-20

10-21

09-22

08-23

16-15

17-14

18-13

19-12

20-11

21-10

22-09

23-08

22-08

21-08

20-08

20-07

08-22

08-21

08-20

07-20

09-19

10-18

11-17

12-16

13-15

14-14

15-13

16-12

17-11

18-10

19-09

09-20

09-21

10-19

20-09

19-10

21-09

24-08

25-08

26-08

08-24

08-25

08-26

15-25

15-24 16-25

17-25

18-25

19-25

15-23

15-22

15-21

15-20

16-19

16-18

15-19

14-20

14-21

14-22

14-23

14-24

14-25

14-26

15-26

16-26

17-26

18-26

20-25

19-26

21-24

22-23

23-22

20-26

21-25

22-24

23-23

24-22

24-21

25-21

25-20

26-2025-19

26-1925-18

26-1825-17

26-1725-16

26-1625-15

26-15

26-14

24-15

25-14

23-15

24-14

22-15

23-14

21-15

22-14

21-14

20-15

19-16

20-14

19-15

18-16

08-19

19-08

15-17

15-18

14-18

14-19

13-19

13-20

13-21

12-21

12-20

13-22

12-22 13-23

12-23 13-24

12-24 13-25

12-25

12-26

13-26

12-27

13-27

12-28

14-27

13-28

15-27

14-28

16-27

15-28

17-27

16-28

17-28

18-27

18-28

19-27

20-27

19-28

20-28

21-26

21-27

22-25

22-26

23-24

23-25

24-24

24-23

25-22

25-23

26-21

26-22

27-20

27-21

27-19 28-20

28-1927-18

28-1827-17

28-17

28-16

27-16

27-15

28-1527-14

28-1427-13

20-20

28-13

28-12

26-13

27-12

25-13

26-12

24-13

25-12

23-13

24-12

22-13

23-12

21-13

22-12

20-13

21-12

20-12

19-14

19-13

18-15

18-14

17-15

18-23

21-22

23-19

22-17

19-18

17-21

08-27

15-15

14-15

15-14

13-14

14-13

24-25

25-24

25-25

28-21

28-22

17-13

30-20

17-12

19-11

22-10

23-10

24-10

25-10

26-10

27-10 28-11

30-10

30-11

30-12

30-13

30-14

30-15

30-16

30-17

30-18

30-19

11-27

10-28

09-29

08-30

07-31

27-11

28-10

29-09

30-08

31-07

19-31

31-19

07-30

18-11

20-10

23-09

24-09

25-09

26-09

27-09

28-09

21-07

22-07

23-07

24-07

25-07

26-07

27-07

28-07

29-07

30-07 31-08

29-10

31-09

31-10

07-21

31-11

07-22

31-12

07-23

31-13

07-24

31-14

07-25

31-15

07-26

31-16

07-27

31-17

07-28

31-18

07-29

08-28

08-29

09-28

09-30

30-09

27-08

28-08

29-08

09-18

10-17

11-16

12-15

15-12

16-11

17-10

18-09

14-16

13-16

13-17

12-17

12-18

11-18

11-23

11-19

10-20 11-21

11-22

10-22

10-23

09-23

11-24

10-24

09-24

11-25

11-2610-25

09-25

09-26

09-27

10-27

10-26

11-28

10-29

11-29

10-30

11-30

19-30

21-29

22-27

24-26

27-22

27-23

16-14

29-21

16-13

18-12

21-11

22-11

23-11

24-11

25-11

26-11

29-11

29-12

29-13

29-14

29-15

29-17

29-18

29-19

29-20

12-30

13-30

15-30

17-30

14-30

16-30

18-30

12-29

20-29

22-28

23-26

13-29

14-29

16-29

18-29

15-29

17-29

19-29

10-31

18-31

20-30

21-28

23-27

26-23

26-24

11-31

12-31

14-31

16-31

13-31

15-31

17-31

08-31

09-31

29-16

20-24

21-23

19-23

18-20

19-17 23-21

23-17

21-17

17-16 22-2120-1918-17

19-22

19-2017-18

17-20

22-1920-17

18-1816-16 21-21

21-19

20-22

21-20

20-23

20-21

18-21

23-18

23-2021-18

19-1917-17 22-22

19-21

22-18

22-2020-18

18-1916-17

17-23

17-22

18-22

17-19

16-20

16-21

16-22

16-23

16-24

17-24

18-24

19-24

20-16

21-16

22-16

23-16

24-16

24-17

24-18

24-19

24-20

15-16

14-17

13-18

12-19

11-20

10-21

09-22

08-23

16-15

17-14

18-13

19-12

20-11

21-10

22-09

23-08

22-08

21-08

20-08

20-07

08-22

08-21

08-20

07-20

09-19

10-18

11-17

12-16

13-15

14-14

15-13

16-12

17-11

18-10

19-09

09-20

09-21

10-19

20-09

19-10

21-09

24-08

25-08

26-08

08-24

08-25

08-26

15-25

15-24 16-25

17-25

18-25

19-25

15-23

15-22

15-21

15-20

16-19

16-18

15-19

14-20

14-21

14-22

14-23

14-24

14-25

14-26

15-26

16-26

17-26

18-26

20-25

19-26

21-24

22-23

23-22

20-26

21-25

22-24

23-23

24-22

24-21

25-21

25-20

26-2025-19

26-1925-18

26-1825-17

26-1725-16

26-1625-15

26-15

26-14

24-15

25-14

23-15

24-14

22-15

23-14

21-15

22-14

21-14

20-15

19-16

20-14

19-15

18-16

08-19

19-08

15-17

15-18

14-18

14-19

13-19

13-20

13-21

12-21

12-20

13-22

12-22 13-23

12-23 13-24

12-24 13-25

12-25

12-26

13-26

12-27

13-27

12-28

14-27

13-28

15-27

14-28

16-27

15-28

17-27

16-28

17-28

18-27

18-28

19-27

20-27

19-28

20-28

21-26

21-27

22-25

22-26

23-24

23-25

24-24

24-23

25-22

25-23

26-21

26-22

27-20

27-21

27-19 28-20

28-1927-18

28-1827-17

28-17

28-16

27-16

27-15

28-1527-14

28-1427-13

20-20

28-13

28-12

26-13

27-12

25-13

26-12

24-13

25-12

23-13

24-12

22-13

23-12

21-13

22-12

20-13

21-12

20-12

19-14

19-13

18-15

18-14

17-15

18-23

21-22

23-19

22-17

19-18

17-21

08-27

15-15

14-15

15-14

13-14

14-13

24-25

25-24

25-25

28-21

28-22

17-13

30-20

17-12

19-11

22-10

23-10

24-10

25-10

26-10

27-10 28-11

30-10

30-11

30-12

30-13

30-14

30-15

30-16

30-17

30-18

30-19

11-27

10-28

09-29

08-30

07-31

27-11

28-10

29-09

30-08

31-07

19-31

31-19

07-30

18-11

20-10

23-09

24-09

25-09

26-09

27-09

28-09

21-07

22-07

23-07

24-07

25-07

26-07

27-07

28-07

29-07

30-07 31-08

29-10

31-09

31-10

07-21

31-11

07-22

31-12

07-23

31-13

07-24

31-14

07-25

31-15

07-26

31-16

07-27

31-17

07-28

31-18

07-29

08-28

08-29

09-28

09-30

30-09

27-08

28-08

29-08

09-18

10-17

11-16

12-15

15-12

16-11

17-10

18-09

14-16

13-16

13-17

12-17

12-18

11-18

11-23

11-19

10-20 11-21

11-22

10-22

10-23

09-23

11-24

10-24

09-24

11-25

11-2610-25

09-25

09-26

09-27

10-27

10-26

11-28

10-29

11-29

10-30

11-30

19-30

21-29

22-27

24-26

27-22

27-23

16-14

29-21

16-13

18-12

21-11

22-11

23-11

24-11

25-11

26-11

29-11

29-12

29-13

29-14

29-15

29-17

29-18

29-19

29-20

12-30

13-30

15-30

17-30

14-30

16-30

18-30

12-29

20-29

22-28

23-26

13-29

14-29

16-29

18-29

15-29

17-29

19-29

10-31

18-31

20-30

21-28

23-27

26-23

26-24

11-31

12-31

14-31

16-31

13-31

15-31

17-31

08-31

09-31

29-16

HOMOGENEOUS (diluted in the fuel) (#1% MA)The GACID experiment in MONJU !

« once through targets » (inert matrix)

multi-recycled «MA-bearing blankets » (# 10-20% MA on UO2)

HETEROGENEOUS:

« DEDICATED STRATA »(ADS)


Am TRANSMUTATION

241Am

242Am

243Am

244Am

242Cm

243Cm

244Cm

241 Pu

242 Pu

243 Pu

239 Pu

240 Pu

238 Pu

-16,02h

-4,96h

239 Np

238 Np

-2,36j

- 10,1h

+ 16,02h

82,7%

17,3%

90% transmuted

30% fissionned

ECRIX H in PHENIX

Metallic FPs

Initial AmO2

18


AN OPTION FOR MA TRANSMUTATION:“Am-bearing blankets”

AM

Pu

U-PuU-AM

FP (Reprocessing Unit)

CORE : UPuO2“BLANKETS” : UAmO2

DIAMINO experiment(Am-loaded UO2 pellets

in MTR)




3-EXPLORATION P&T (minor actinide recycle)

4- ALTERNATIVE PROCESSES ???(« dry » processes…)

FUEL CYCLE TECHNOLOGIES : GUIDELINES FOR R&D…

19


basic chemistry Fuel dissolution

Partitioning processesConversion processesActinide compounds

New extractants

Waste Conditioning,

THE ATALANTE FACILITYDemonstration hot runs



-reactors?



20


2009 2010 2011 2012 2013 2014 2015 2016 2017

Decision to continue

Preliminary choice of options

ASTRID PROTOTYPE Schedule

Decision to build

Conceptualdesign -1

Conceptualdesign -2

Basic design

Fuel loading

Detailed design& Construction

ASTRID

Facilities

Feasibility Report on minor

actinides partitioning

Position Report on minor actinides partitioning and transmutation

Core manufacturing

workshop (AFC)

MA bearing fuels fabrication facility

(ALFA)


ASTRID FUEL CYCLE

Init

ial

feed

ASTRID

Fuel Fabrication

Spent fuel processing

1st goal : Pu & U multirecycle

21


ASTRID FUEL CYCLEIn

itia

l fe

ed

ASTRID

Fuel Fabrication

Spent fuel processing

MA

1st goal : Pu & U multirecycle2nd : Minor Actinide (Am) recycle


FR DEPLOYMENT :MANY DIVERSE OPTIONS…

0

10

20

30

40

50

60

70

2000 2020 2040 2060 2080 2100 2120 2140

REP actuels

EPR

RNR

Année

Puissance installée (GWe)

Progressive substitution FRs/LWRs from 2040…???

22


FR DEPLOYMENT :MANY DIVERSE OPTIONS…

0

10

20

30

40

50

60

70

2000 2020 2040 2060 2080 2100 2120 2140

REPactuelsEPR

Année

Puissance installée (GWe)

0

10

20

30

40

50

60

70

2000 2020 2040 2060 2080 2100 2120 2140Année

Puis

sance

inst

allé

e (G

We)

EPR

RNR

REP actuel

TOTAL

Scénario F30 : déploiement de RNR assisté par un parc REP de 60 GWé

0

20

40

60

80

100

120

140

2010 2030 2050 2070 2090 2110 2130 2150Années

Pui

ssan

ce in

stal

lée

(GW

é)

REP actuels

EPR

RNR

TOTAL

FRs complementing LWRs for Pu management and fleet evolving later according to energy needs…


FLEET AND FUELS WILL EVOLVE…

processes & technologies : flexible, efficient, cost-effective,clean, proliferation-resistant…

(?)

(?)

(HBU, MOX)

(feeding FRs)

(multi-recycle FRs)

(minor actinide recycle? )

TODAY

THEN?

THEN?

THEN?

LWRs FRs

Date post:	27-Aug-2018
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