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Improving the actinides recycling in closed fuel
cycles, a major steptowards nuclear energy
sustainability
| PAGE 1CEA | 10 AVRIL 2012
Stéphane BOURG(1),Christophe POINSSOT(1),
Dominique WARIN(2)
(1) CEA Marcoule / Nuclear Energy Division,RadioChemistry & Processes Department
(2) CEA Saclay / Nuclear Innovation and Industrial Support Program Division,
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
OUTLOOK
1. What means referring to sustainability?
2. Environmental drivers: preserving the naturalresource
3. Societal drivers: improving the social acceptance
4. Conclusion: the rationale of the future fuel cycles
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
Green economy
Reference
case
About the rationale for a new energy mix
���� Necessity to
mitigate the
global climate
change
���� Energy needs will at least double
Wor
ld E
nerg
y O
utlo
ok, A
IE 2
008
0 100 200 300
coal
coal-gas combined cycle
oil
liquid natural gas
thermal solar
tidal power
photovoltaic
wind power
geothermal power
nuclear power
hydraulic power
gCO2/KWh
construction
operation
���� low-carbon energies should increase their contribution
Sustainability requiresa new energy mix
based on carbon-free energies
PAGE 3
10 000 5 000 0
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
Towards sustainable future energy systems
4
« Sustainable development is development that meets the needs of the present without compromising the ability of future generations to meet their own needs. (…) »
(Bruntland's commission, 1987)
• GHG-free energy
• Preservation of natural resource
• Low environmental footprint
• Predictable, stable and limited energy cost
• Economic stability through energetic
independence
• Highest level of safety and reliability
• Consensual choice of the society
• Promote the international stability
3 main drivers to consider
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
���� Environmental drivers: preserving the natural resource
�Very low carbon footprint�Uranium conventional resource
Limited for the far-future at a reasonable price (130$/kg U)Lifespan ~1-2 centuries (current consumption 75kt/y)
� However, global efficiency iscurrently very low: ~0.7%
Only ~70t from the initial ~9500t of U is effectively used
� Need for increasing the sustainability
Preserving U resource for future generationsLimiting the front-end activities
5
Uranium ore
~9500t
depleted U(0.2 – 0.5% 235U)
8300t
1200t 1200t
430 TWhe
Spentfuel
~9t 235U~1122t 236+238U~14t Pu~55t FP+AM
56t 235U1144t 238U
(Once-through)
Rough estimates derived from French Fuel cycle assuming no recycling
∆U~70t
Efficiency~0.7%
(NEA 2008)
(derived from EDF, 2009)
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
Saving natural resource ���� recycling Actinides
�Spent nuclear fuel is not a wasteMainly contains actinides that can beused to produce electricity
In PWR, fissile 235U, 239PuIn FNR, fissile + fertile
Saving natural resource � recyclingvaluable actinides
� Increase of SNF inventory in storage is a current and significant risk
Up to now, only ~30% of dischargedSNF worldwide has been reprocessed (~90 000tHM) Most of SNF is currently stored
Pool � dry storage
FP 4.55%
93.0% 238U0.75% 235U0.54% 236U
0,76% oddPu0,41% evenPu
The sole ultimate waste
regarding French Law
(28th June 2006)
(AIEA, Fukuda et al., 2003)
6
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
1st step towards sustainability: the Pu mono-recycling
7
� Allows saving 17% of U resource� Allows efficient conditioning of HLW
Nuclear glass lifetime demonstrated to be> 500ky in repository
� Allows a significant decrease of wasteburden:
No Pu in waste anymoreLifetime / radiotoxicity decreased by one order of magnitude
0,1
1
10
100
1000
10000
10 100 1000 10000 100000 1000000
Temps (années)
Rad
ioto
xici
té r
elat
ive
102 105 106104103100,1
1
103
104
Time
Relative
radiotoxicity
10
102
U-ore
99,9% of Pu
1200t
10t
8000t
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
Beneficial effect on repository performance
� A major difference between bothIRF is a significant penality for SNF
In particular for any incidental scenario where wasteform is of great significance
Performance of the SNF matrix can besignificantly altered if it becomes oxidising
Spent nuclear fuel (considering solubility-controlled dissolution) Nuclear glass
IRF penality
8
IRF: Instant Release Fraction (129I, 36Cl…)
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
Beneficial effect for the overall environmentalfootprint
9
� Improvement of the global environmentalfootprint
Results from LCA
� Sole indicators to increase are the RN releases
No significant impact
Evolution from OTC to TTC
85Kr
14C129I
Σatm=6µSv/yr
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
���� Increasing efficiency requires shiftingtowards fast neutrons
�Current PWR reactors do not allow an efficient Pu multi-recycling
Increase of non-fissile even Pu isotopes, Low consumption of U through captures
�Neutrons with higher energies allow a better use of U and Pu
neutron capture by 238U � 239Pu fission of every Pu isotopes � MA inventory (=waste)
�Fast neutron reactors allowMulti-recycling of Pu The use of the depleted U stockpile
Theoretically, no need for additional natural U resource � front-end
�Very significant increase of efficiency: from 0.7 to > 80%
σσσσfission /σσσσcapture
10
LWRFNR
0
40
80
120
160
200
Gen 1 Gen 2 Gen 3 Gen4
Ton
nes
Una
t/GW
e-an
sans recyclageavec recyclage
UNGG PWR EPR
160
U n
at(t
) / G
We.
year
200
50
120
80
40
FNR
With
recycling
1t/yr of 238U is sufficient to produce 1 GWe
Once-through cycleTwice-through cycle
Multi-recycling cycle
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
�Progressive introduction of FNR allows the multi-recycling of Pu
�Feasibility of LWR + FR MOX fuels reprocessing already demonstrated� R&D to adapt the processes to the specificity of FNR fuels
2nd step towards sustainability: the stepwise development of 4 th generation fuel cycle
11
U and Pu multi-recycling in a full FR fleet
( principle values, self-balanced fleet, 60
GW/y)
450t
40t
40t
90t
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
���� The societal drivers: Improving the social acceptance
� First: safety has to be kept at the highest level
� Second: waste long-termmanagement is not convincing for part of the public opinion
Nuclear waste = Achille's heel of nuclear energy (due to lifetime)Decreasing the waste lifetime mayimprove the social acceptance
� Recycling Pu already yields a verysignificant benefit
� Further improvement requires the recycling the MAs
12
Eurobarometer 2008: % of EU citizens supporting nuclear energywith/without a permanent and safe solution for the HLW
Without With
Pu
Am
Cm
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
0,1
1
10
100
1000
10000
10 100 1000 10000 100000 1000000
Temps (années)
Rad
ioto
xici
té r
elat
ive
102 105 10610410310
0,1
1
10
102
103
104
time
toxicity
U ore
Recycling the minor actinides, a potential contribution for decreasing the waste b urden
�Allows decreasing the waste lifetime and toxicity
�Allows the stabilization of the MA inventory in the whole fuel cycle
�Allows the preservation of the valuable repository resource
of the heat load �
density of the repository With Am recycling, reduction of the repository volume by a factor up to 8
Very significant increase of the repository "lifespan"
13
HLW: 1200 haHLW: 160 ha
Am
rec
yclin
g
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
Two main Minor Actinide recycling options
T
U
U Pu AM
FP
Grouped recycling
TMA
U Pu
FP
Heterogeneous recycling
U
Homogeneous recycling �
grouped recycling �
GANEX processes
Heterogeneous recycling �
enhanced partitioning �
DIAMEX/SANEX processes
Moderated core target or blanket in periphery
of the core with MA content ~10-20%
MA concentration ~1%, diluted in
standard fuel in the whole core
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Specific extraction processes have been developed and qualified14
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
The rationale of the various MA separation processe s
U Product
Pu Product
U Product
Pu Product
U Product
Pu ProductCOEX
U Product
UPu Product
An(III) + Ln(III)-
An(III)/Ln(III)separation
An(III) + Ln(III)-
An(III)/Ln(III)separation
An(III) + Ln(III)- coextraction
An(III)/Ln(III)separation
An(III) + Ln(III)-
An(III)/Ln(III)separation
(DIAMEX) (r-SANEX)
Am,CmAmAmAm
Am selective
Stripping
(EXAm)
GANEX 1
GANEX 2
U
Pu Np Am Cm
Am CmAn(III) selective
Stripping
(i-SANEX)
Am Cm
Homogeneous recycling= grouped separation
GANEX
Heterogeneous recycling= enhanced partitioning
DIAMEX/SANEX
AmAm
U
U,Np,
Pu,Am,
Cm
TMA
U Pu
FP
U
T
U Pu MA
FP
U
15
U,Pu
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
Recycling the sole Am through the EXAm process
1- Co-extraction Am and light Ln (III) with
DMDOHEMA + HDEHP
+ TEDGA in aqueous phase
2- Stripping of Am with HEDTA + Citric acid
(pH=3-4)
NO
N
O O
Efficiency demonstrated with hot test performed in
Atalantein 2010 on ~5kg
spent fuel
> 98.5% AmFD(Cm) = 500
OO
OHOP
16
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
The rationale of future nuclear fuel cycles in view of sustainability
Gen. II & III
1980 2000 2200 2040 2060 2080 2100
Gen. IV
…+ MA recycling
Pu-monorecycling
Pu-multi-recyclingPu-mono-recycling- Twice-Through Cycle- LWR reactors
- Pu-recycling in MOX fuel
Pu multi-recycling- Multi-Through Cycle- Fast-Reactors (FR)
- Pu multi-recycling
Pu+MA multi-recycling- Fast Reactors (FR)
- Pu multi-recycling
- MA burning
Gen. IV
Main incentives
- 1st step towards U
resource saving
- Efficient waste
conditioning
Main incentives
- Major resource saving
- Energetic independence
- Economic stability
Main incentives
- Decrease of waste burden,
- Optimisation of the disposal
- Public acceptance
TOWARDS INCREASING SUSTAINABILITYDates are purely indicative
Breakthrough=reactors
Breakthrough=cycle
Onc
e-th
roug
hcy
cle
17
Nuclear Energy DivisionRadioChemistry & Processes Department
French-Swedish Seminar on Future Nuclear Systems
Stockholm, December 3rd, 2013
Conclusion: on the sustainability of fuel cycles …
�Sustainability of current fuel cycles can bestrongly improved by recycling the actinides
Preserve the uranium resource for future generations
Twice-through cycle is beneficial first stepalready allows saving 17% natural uraniumFor a similar economic costWith a positive impact in terms of wastevolume, lifetime and long-term performances and environmental footprint
�Further Improvement would requireImproving uranium resource preservation
Use of 238U through Pu-multi-recycling in FNR, Reduced need for any U-mining activities
Decreasing waste burden towards future generations
Minor actinides transmutation
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3rd step: MA recycling to decrease burden to
future generations and increase acceptance
1st and 2nd step: Pu recyclingto increase natural resourcesaving and promote stable
and predictable energy costs
Recycling the actinides is the cornerstone of any susta inable fuel cycle!
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