French fuel cycle strategy and partitioning and ... · DEN 9-IEMPT NIMES September 26 , 2006 6...
Transcript of French fuel cycle strategy and partitioning and ... · DEN 9-IEMPT NIMES September 26 , 2006 6...
1DEN 9-IEMPT NIMES September 26 , 2006
French fuel cycle strategy
and partitioning and transmutation programme
Philippe PRADELNuclear Energy Division
Charles COURTOISNuclear Energy Division / Waste Management Research Program
2DEN 9-IEMPT NIMES September 26 , 2006
UP2-800 : 1994 : Commissioned for PWR fuelsCapacity : 800 t/y(Its an upgrade of UP2-400)Dedicated to French customers (EDF)
UP3 :1990 : Commissioned for PWR fuelsCapacity : 800 t/yDedicated to foreign customers
Reaching maturity : the 90’
Reprocessing :The La Hague integrated site
3DEN 9-IEMPT NIMES September 26 , 2006
Relative contribution to totalradiotoxicity after 1 000 years
Fission products
Minor actinides
Plutonium
Cladding & structural materials : medium level & long lived waste
Recyclable materials (95 %)Fission products :25 kg
Minor actinides :~ 0,5 kg
Vitrified HL radwaste (5%) Plutonium :
5 kg (1 %)
Uranium :
470 kg (94 %)
Spent fuel processingSpent fuel processing
Current scheme for the PUREX process
4DEN 9-IEMPT NIMES September 26 , 2006
Waste management
Heat load of the TRU Potential radiotoxicity
(241Pu ---> 241Am ---> 237Np)
• Urgent matter for public acceptance of nuclear energy• Recycling minimizes both the repository space and
environmental impact
1st contributor : Pu ; 2nd contributor : Minor Actinides (MA)
5DEN 9-IEMPT NIMES September 26 , 2006
Bitumen
Grout concreteTechnological waste
Glass
ConcreteHulls & end fittings
CompactionHulls, end fittings &technological waste
Volume of waste in m3/tHM
0
3
2
1
4
1995 20001989(Design)
0.1 % 0.1 %1 % 100 %Pu losses
Fuel treatment optimization : Specific waste volume for the UP3 plant
Conditionedspent fuel
6DEN 9-IEMPT NIMES September 26 , 2006
Which goals?Goal 1 research : solutions that would allow partitioningand transmutation of long lived radionuclides present in HL LL waste and reduce the overall radwaste quantity and toxicity.
Goal 2 research : feasibility of reversible or irreversible repository in deep geological formations.
Goal 3 research : conditioning processes and feasibility of long term storage, above-grade or below-grade.
Deadline set in law : 2006
The Law of December 30, 1991
7DEN 9-IEMPT NIMES September 26 , 2006
Partitioning : key nuclides
minor actinides : Am - Cm - Npmajor contributors to long term radiotoxicinventory;
fission products : I - Cs - Tc– long lived isotopes significantly present in spent fuel,– with a potential for mobility within rock formations;
processes : hydro-metallurgy (consistent with PUREX) and pyro-chemistry (more innovative);
partitioning of nuclides present in the already vitrified HL waste would be rather difficult.
8DEN 9-IEMPT NIMES September 26 , 2006
Research steps
Fundamental research : a wide co-operative framework- exploration : new extracting systems ;- fundamentals : in-depth study of mechanisms
at work ;
Applied research :- process design ;- lab experiments on actual spent fuel
material ;- « demonstration » experiments :
integration, representativeness, long-lastingperformance ;
A true challenge : a sophisticated partitioning chemistry under highly radioactive conditions.
A few hundreds
of new molecules
Scale : 1/10000
Scale : 1/100 à 1/1000
9DEN 9-IEMPT NIMES September 26 , 2006
Actinides partitioning : research path used
Spent fuel
U, Pu Np
Cm
AmLn
PUREXPUREX
SANEXSANEX
Fissionproducts DIAMEXDIAMEX CO-EXTRACTION
of An et LnCO-EXTRACTION
of An et Ln
PARTITIONINGbetween An & LnPARTITIONING
between An & Ln
1
H2
He3
Li4
Be5
B6
C7
N8
O9
F10
Ne11
Na12
Mg13
Al14
Si15
P16
S17
Cl18
A19
K20
Ca21
Sc22
Ti23
V24
Cr25
Mn26
Fe27
Co28
Ni29
Cu30
Zn31
Ga32
Ge33
As34
Se35
Br36
Kr37
Rb38
Sr39
Y40
Zr41
Nb42
Mo43
Tc44
Ru45
Rh46
Pd47
Ag48
Cd49
In50
Sn51
Sb52
Te53
I54
Xe55
Cs56
Ba Ln72
Hf73
Ta74
W75
Re76
Os77
Ir78
Pt79
Au80
Hg81
Tl82
Pb83
Bi84
Po85
At86
Rn87
Fr88
Ra An104
Rf105
Db106
Sg107
Bh108
Hs109
Mt110
Uun
LANTHANIDES
57
La58
Ce59
Pr60
Nd61
Pm62
Sm63
Eu64
Gd65
Tb66
Dy67
Ho68
Er69
Tm70
Yb71
Lu
ACTINIDES
89
Ac90
Th91
Pa92
U93
Np94
Pu95
Am96
Cm97
Bk98
Cf99
Es100
Fm101
Md102
No103
Lr
NOYAUX LOURDS PRODUITS D’ACTIVATION
PRODUITS DE FISSION PRODUITS DE FISSION ET D’ACTIVATION
10DEN 9-IEMPT NIMES September 26 , 2006
The ATALANTE facility…
From basic studies to demonstrative experiments …… up to kgs of spent fuel
11DEN 9-IEMPT NIMES September 26 , 2006
Am, Cm, Np, Tc, I et Cs partitioning :lab scale results
Americium & curium : recovery ratio up to 99,9%for Am & 99,9% for Cm ;
long-lasting performance tested (« accelerated » simulation within an irradiation loop) ;
confirmation test with the use of « industrial » technology have been successful in 2005 ;
Neptunium : recovery ratio up to 99% ;
Technetium : recovery ratio from 45 à 90%;
Iodine : - recovery ratio > 97% with PUREX; - additional recovery up to ~ 99% possible ;
Caesium : recovery ratio > 99,8%, with the use of the calixarene extractant.
N
O
C2H4
N
O
C8H17
CH3CH3
C8H17O
C6H13
DMDOHEMA
OP
O
O O
HHDEHP
N
O
O
ON
OH
OH
OHOHHEDTA
12DEN 9-IEMPT NIMES September 26 , 2006
Conclusion …. for partitioning R&D
A large scope for research :from fundamentals to applications;
- the actinides: the key target;
- partitioning of nuclides present in the already vitrified HL waste is no more considered.
- a scope wide open : (numerous options explored and co-operations);
- feasibility of pyro-chemical processes not yet demonstrated;
- molecules and partitioning processessuccessfully tested at the lab scale;
- and successfully tested in 2005 within the Atalante hot cells (to replicate an industrial-like set-up);
- a research booster for partitioning and actinides chemistry;
- further steps will be required prior to any industrial implementation.
Atalante in Marcoule
CBP
13DEN 9-IEMPT NIMES September 26 , 2006
Transmutation : capture & fission
Making use of neutron flux (within a reactor) to turn LL radionuclides into stable or shorter-lived isotopes through neutron capture or fission reactions.
For actinides, fission reaction, not neutron capture, must be considered.
For fission products, neutron capture reactions are observed resulting in stable or short-lived nuclides.
14DEN 9-IEMPT NIMES September 26 , 2006
Transmutation output according to neutron spectrums used
- Two recycling modes have been considered : homogeneous mix within the nuclear fuel or heterogeneous in targets at higher concentrations;
- There is obviously a net advantage in using a fast neutron flux to get higher fission rate, however increasing the fission rate requires multiple recycling ;
Fast neutron flux and spectrum are more efficient to transmute actinides through fission reaction.
R&D on basic nuclear data :Nuclear data obtained on actinides cross-sections is used to rank the
transmutation potential of various systems.
15DEN 9-IEMPT NIMES September 26 , 2006
Transmutation tools : existing reactors?(1/2)
• PWR : the scientific feasibility to transmute americium is established; however more enriched uranium is needed in the fuel and more curium is produced as a result, which is not recyclable in PWR;
PHENIX
FNR should be able to help eliminate minor actinides produced in the existing PWR fleet of reactors and to manage those produced within FNR.
• FNR : minor actinides transmutation is established with no detriment on the normal operating conditions of the reactor.
REP
16DEN 9-IEMPT NIMES September 26 , 2006
Transmutation tools : future reactors ? (2/2)
• FNR-gas (GEN IV) :- up to 5 % of minor actinides
concentration in fuel could be acceptable (only limited by the fuel behaviour under irradiation);
• Hybrid systems (ADS) : 5th et 6th
European FP, CEA/CNRS collaboration :- significant R&D work is on-going,- ADS concept is highly complex,
however there appears to be so far no show-stoppers towards demonstrating the feasibility of an experimental facility,
- nevertheless, stumbling stones have been highlighted.
ADS
Génération IVInternational
Forum Members
Génération IVInternational
Forum Members
U.S.A.U.S.A. Génération IVInternational
Forum Members
Génération IVInternational
Forum Members
U.S.A.U.S.A.U.S.A.U.S.A.U.S.A.U.S.A.
ArgentinaArgentinaArgentinaArgentinaArgentinaArgentinaArgentinaArgentina
BrazilBrazilBrazilBrazil
CanadaCanada
BrazilBrazilBrazilBrazil
CanadaCanadaCanadaCanadaFranceFranceFranceFrance
JapanJapanJapanJapan
CanadaCanadaFranceFranceFranceFrance
JapanJapanJapanJapan
South AfricaSouth AfricaSouth AfricaSouth AfricaSouth AfricaSouth Africa
UnitedUnitedKingdomKingdom
South AfricaSouth Africa
UnitedUnitedKingdomKingdomUnitedUnitedKingdomKingdom
South KoreaSouth Korea
SwitzerlSwitzerlandand
SwitzerlSwitzerlandand
E.U.E.U.E.U.E.U.
17DEN 9-IEMPT NIMES September 26 , 2006
Nuclear fuel for transmutation : current R&D programmesReactors in use or considered :
- irradiation reactors : HFR,SILOE;- fast neutron research reactors :
• PHENIX,• JOYO, MONJU (Japan),• BOR 60 (Russia).
Design and fabrication of experimental fuel, and associated safety case ;
- irradiation (minimum 5 years),- non destructive and destructive examinations,- 35 irradiation experiments have been conducted or
are on-going.
PHENIX
Results validation :- actinides concentration and burn-ups;- fission rate for one cycle :
i.e. 70% of the americium contained in one target has undergone fission.
18DEN 9-IEMPT NIMES September 26 , 2006
Conclusion … for transmutation
the feasibility of transmuting actinides such as Am and Np is recognised in fast neutron reactors according to experiments run in SFR;
ADS systems are quite complex, and their technical and economical viability for actinides transmutation is yet to be proven;
transmutation of technetium 99 is feasible, but not efficient;
transmutation of caesium 135 is no longer pursued;
transmutation of iodine 129 is not currently feasible.
Reducing the ultimate waste radiotoxicinventory is possible with implementinga continuous improvement step-wise process;
Goal 1 cannot apply to current ultimatewaste (vitrified).
An international expert peer-review report is available
1
0,1
10
100
1000
10000
10 100 1000 10000 100000 1000000Temps (années)
Rad
ioto
xici
té rela
tive
PFAM +PF
Combustible usé( Pu+ AM + PF)
Minerai uranium naturel1
0,1
10
100
1000
10000
10 100 1000 10000 100000 1000000Temps (années)
Rad
ioto
xici
té rela
tive
Combustible usé(U + Pu +Actinides Mineurs + Produits de Fission)
Actinides Mineurs+ Produits de Fission
Produits de Fission
19DEN 9-IEMPT NIMES September 26 , 2006
Future nuclear systems for a nuclear renaissance
• It clearly means fast reactors for sustainability,
• Sodium fast reactor is more mature
• Gas fast reactor is an alternate track
• Minor Actinides recycling may be a progressive approach
20DEN 9-IEMPT NIMES September 26 , 2006
ReferencesPresident Chirac statement (Jan 06) : « A number of countries are working on future generation reactors, to become operational in 2030-2040, which will produce less waste and will make a better use of fissile materials. I have decided to launch, starting today, the design work by CEA of a prototype of the 4th generation reactor, which will be commissioned in 2020.We will naturally welcome industrial or
international partners who would like to get involved. »
The Radwaste Management Act (June 06) :“Transmutation : studies to be carried out within the R&D framework of future nuclear energy and ADS systems - aiming at 2012 for the technical feasibility evaluation (industrial level), and 2020 for the commissioning of a prototype”.
21DEN 9-IEMPT NIMES September 26 , 2006
Nuclear Fuel Cycle Goals
R T
Ude
FP
U Pu MA
R T
Ude
MAU Pu
FPR T
Ude
FP MA
U Pu
Homogeneousrecycling (GenIV)
Heterogeneousrecycling
U & Pu recycling
Natural resources conservation
Waste minimisation
Proliferation resistance
All paths should be kept available, they could be used in a sequence.
50 more electricityproduced with the same
quantity of naturaluranium
22DEN 9-IEMPT NIMES September 26 , 2006
The next generations of reprocessing facilities
UOx – LWR fuel1000 t/yearPUREX process MOX & UOx LWR fuels
Higher throughputIntegrated fuel processing and recycling : COEXAdvanced separation technologies
LWR & FR fuels> 2000 t/yearNew technologies
1990
∼ 2020
> 2040
Gen II
Gen III
Gen IV
23DEN 9-IEMPT NIMES September 26 , 2006
Looking for a long term management strategy?Results already in use :
- improved industrial facilities and processes;- since 1991, significant waste volume reduction
(by a factor of 6);- feasibility of disposal
A continuous improvement process to be continued:- for opening the scope of possible solutions;- and defining future electricity generating systems.
A new bill.Ufrom mine
Actinides
Comb.usé
Ultimatewaste
FP
GEN IV NR
Traitement et
Re-fabrication
U
Actinides
Spent.fuel
GEN IV NR
-
- Minimising ultimate waste
- Optimal use of energy-bearing natural resources
- Proliferation resistance