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8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 1
Expert Group on
Impact of Advanced Nuclear Fuel Cycle Options on Waste Management Policies
A joint NDC-RWMC undertaking, with NSC support
progress report by J.M. Cavedon, chairperson
8th Information & Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation
Las Vegas, 9-11 November 2004
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 8
RWMC - Integrated Group for Safety Case statement
Conclusions of the IGSC Topical session ”Potential Impacts of Partitioning and Transmutation on Long-term Waste Management and Disposal” 6 Nov 2002
P&T will not eliminate the need for geological disposal of radioactive waste but has the potential to reduce volume, radiotoxicity and long-term heat production of the highest activity waste.
… From the IGSC point of view, on the one hand no showstoppers for
the new reactor concepts appeared even if there is not sufficient information on new waste types, on their characterisation, and especially on their long-term behaviour and in-situ performance.
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 9
RWMC- Integrated Group for Safety Case statement
Few, if any, full system studies have been performed to get the larger potential impacts picture including costs. From the IGSC point of view it is necessary to perform comprehensive systems studies and not to restrict the considerations to inventories and heat production of the highest activity waste.
If a society is to understand the implications of introducing this technology in the future, it must also be informed by studies of all aspects of the endeavour important to society, such as cost, land and resource commitment, and worker and public safety
Suggested interaction between RWMC and NDC is highly recommended, especially on the last two points
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 10
Mandate of the Expert Group „Impact“
The study would aim at analysing a range of future fuel cycle options from the perspective of their impact on waste repository demand and specification. The study would focus on:
Assessment of the characteristics of radioactive wastes arising from advanced nuclear fuel cycle options.
Repository performance analysis studies using source terms for waste arising from such advanced nuclear fuel cycles.
Identification of new options for waste management and disposal.
Mandate approved both by NDC and IGSC
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 11
Complete Fuel cycles
HLW, ILW, LLW
include all waste
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 14
Working Group 1, fuel cycle scenarios
WG1 defines the fuel cycles to be studied and the material flow sheets to be produced (mass flows, composition and radiotoxicity) including time scales to be considered.
Servais PILATE, BE Peter WYDLER, CH Alain ZAETTA, FR, Chair Marc DELPECH, FR Tetsuo IKEGAMI, JP Jae-Hyung YOO, KO Anatoly LUKINYHK, RU Jose Enrique GONZALEZ, SP Armando URIARTE, SP Colin ZIMMERMAN, UK Michel HUGON, EU Enric PLA, EU Rudolf BURCL, IAEA
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 15
Working Group 2, waste and repositories
WG2 mainly based on the work of the first group will define of waste management aspects to be studied; such as amount and nature of wastes (LLW, ILW, vitrified, new waste forms), chemical toxicity, time scale to be considered.
Jan MARIVOET, BE Peter WYDLER, CH Ludger LAMBERS, DE Aleksandra SCHWENK-FERRERO, DE Jean-Marc CAVEDON, F and CH, chair Marku ANTTILA, FI Mario DIONISI, IT Kwan Sik CHUN, KO Armando URIARTE, SP Samantha KING, UK Rudolf BURCL, IAEA Jose Luis GONZALEZ GOMEZ, IAEA
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 16
Working Group 3, economics and integration
WG3 defines what kind of economical and feasibility studies will be performed. An important task for this working group is to integrate the relevant and available information.
Bill HALSEY, USA, chair Christine LOAEC, FR Leroy STEWART, USA Kwang Seok LEE, NEA and KO Timo HAAPALEHTO, NEA
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 17
Parties interested in the EG „Impact“
12 countries
Belgium Finland France Germany Italy Japan Korea Russia Spain
Switzerland United Kingdom United States of America
2 international organisations
IAEA European Union
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 20
Fuel cycle scenarios
3 families of increasing recycling capability
Current industrial technology and extension• 1a open cycle• 1b Pu monorecycle in PWR• 1c Pu and Np monorecycle in PWR• 1d Dupic in PWR + Candu
Partially closed fuel cycle• 2a Pu multirecycle in PWR• 2b Pu and Am multirecycle in PWR• 2c Pu and Am mutirecycle in PWR+FR
Fully closed fuel cycle• 3a TRU multirecycle in FR• 3b all An burnt in double strata with ADS• 3c all An recycle in FR
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 21
Current industrial technology and extension
Reactors Fuel cycle (type of reprocessing)
Nature of wastes
N°1a PWR (UOX) 60 GWd/tHM Open cycle UOX Fuels, ILW, LLW
N°1b PWR (UOX) PWR (MOX)
60 GWd/tHM 60 GWd/tHM
UOX reprocessed (PUREX) Pu once cycling in MOX
HLW, ILW, LLW MOX fuels
N°1c PWR (UOX) PWR (MOX)
60 GWd/tHM 60 GWd/tHM
UOX reprocessed (UREX) Pu, Np once cycling in MOX
HLW, ILW, LLW MOX fuels
N°1d PWR (UOX) CANDU
35 GWd/tHM 15 GWd/tHM
UOX reprocessed (OREOX) HLW, ILW, LLW UOX fuels
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 22
Cycle 1c : (Pu + Np) mono-recycle in PWR
Scheme 1c UOX reprocessed (UREX) – Pu,Np once cycling in MOX Fuel Characteristics and Mass Flows (kg/TWhe)
PWR 90 %
PWR 10 %
U nat : 18 549 kg
Enrichment
U dep : 16 714 kg
UOX FUEL 1 835 kg
MOX + Np FUEL
215 kg
UREX UOX 1 835 kg
STORAGE MOX 215 kg :
U : 182 kg Pu : 16.8 kg Np : 0.84 kg Am : 1.43 kg Cm : 0.29 kg
PF 14 kg
DISPOSAL Pu : 0.023 kg Np : 0.002 kg Am : 1.4 kg
Cm : 0.25 kg PF : 116 kg
Pu : 23 kg Np : 1.7 kg
Uirr
190 kg
1 720 kg
U dep : 16 524 kg
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 23
Fuel cycle scenarios
3 families of increasing recycling capability
Current industrial technology and extension• 1a open cycle• 1b Pu monorecycle in PWR• 1c Pu and Np monorecycle in PWR• 1d Dupic in PWR + Candu
Partially closed fuel cycle• 2a Pu multirecycle in PWR• 2b Pu and Am multirecycle in PWR• 2c Pu and Am mutirecycle in PWR+FR
Fully closed fuel cycle• 3a TRU multirecycle in FR• 3b all An burnt in double strata with ADS• 3c all An recycle in FR
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 24
Partially closed fuel cycle
Reactors Fuel cycle (type of reprocessing)
Nature of wastes
N°2a PWR (UOX) PWR (MOX-EU)
60 GWd/tHM 60 GWd/tHM
UOX & MOX-EU reprocessed (PUREX) Pu recycling
HLW, ILW, LLW
N°2b PWR (UOX) PWR (MOX-EU)
60 GWd/tHM
60 GWd/tHM
UOX and MOX-EU reprocessed (Advanced PUREX) Partitioning: Am and Cm Cm storage Pu and Am recycling in MOX-EU
HLW, ILW, LLW
N°2c PWR (UOX) FR (MOX)
60 GWd/tHM
140 GWd/tHM
UOX and MOX reprocessed (Advanced-PUREX) Partitioning: Am and Cm Cm storage Transmutation: Am once through
HLW, ILW, LLW Targets
Variant without Am targets
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 25
Scheme 2a UOX and MOX-EU reprocessed (PUREX) – Pu recycling Fuel Characteristics and Mass Flows (kg/TWhe)
PWR 74%
PWR 26%
U nat : 17 935 kg
Enrichment
U dep 15 954 kg
UOX FUEL 1 475 kg
MOX-UE FUEL 575 kg
PUREX
UOX et MOXUE : 2 050 kg
DISPOSAL Np : 1.6 kg Pu : 0.07 kg Am : 5.9 kg Cm : 1.3 kg PF : 128 kg
Pu : 69 kg Uirr : 1 844 kg
Cycle 2a : Pu multirecycled in PWR
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 26
Fuel cycle scenarios
3 families of increasing recycling capability
Current industrial technology and extension• 1a open cycle• 1b Pu monorecycle in PWR• 1c Pu and Np monorecycle in PWR• 1d Dupic in PWR + Candu
Partially closed fuel cycle• 2a Pu multirecycle in PWR• 2b Pu and Am multirecycle in PWR• 2c Pu and Am mutirecycle in PWR+FR
Fully closed fuel cycle• 3a TRU multirecycle in FR• 3b all An burnt in double strata with ADS• 3c all An recycle in FR
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 27
Fully closed fuel cycle
Reactors Fuel cycle (type of reprocessing)
Nature of wastes
N°3a PWR (UOX) FR (metal)
50 GWd/tHM 140 GWd/tHM
UOX reprocessed (UREX) Metal reprocessed (PYRO) Partitioning: TRU (Pu, Np, Am & Cm) Transmutation: TRU homogeneous
HLW, ILW, LLW
N°3b PWR (UOX) PWR (MOX) FR (MOX) ADS (nitride)
50 GWd/tHM 50 GWd/tHM
185 GWd/tHM 150 GWd/tHM
UOX and MOX reprocessed (PUREX) Pu once-recycling in PWR (MOX) Pu multi-recycling in FR Partitioning: Pu & MA (Np, Am & Cm) Transmutation: Pu & MA homogeneous ADS fuel reprocessed (PYRO)
HLW, ILW, LLW
Variant PWR (UOX) ADS (nitride)
50 GWd/tHM 150 GWd/tHM
UOX and MOX reprocessed (PUREX) Partitioning: Pu & MA (Np, Am & Cm) Transmutation: Pu & MA homogeneous ADS fuel reprocessed (PYRO)
HLW, ILW, LLW
N°3c Fast reactor
Variant 1 GCFR
(Gas Cooled Fast Reactor)
100 GWd/tHM Nitride reprocessed (PYRO) Partitioning: MA (Np, Am and Cm) Transmutation: MA homogeneous
HLW, ILW, LLW
Variant 2 LMFR
(Liquid Metal Fast rector)
140 GWd/tHM MOX reprocessed (Advanced PUREX) Partitioning: MA (Np, Am and Cm) Transmutation: MA homogeneous
HLW, ILW, LLW
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 28
Cycle 3b : double strata
Scheme 3b “Double Strata”
UOX and MOX reprocessed (PUREX) – Pu once recycling in PWR (MOX) – Pu multi recycling in FR Metal reprocessed (PYRO) – TRU partitioning and homogeneous transmutation – ADS fuel reprocessed (PYRO°
Fuel Characteristics and Mass Flows (kg/TWhe)
PWR (66%)
PWR (9.8%)
PUREX (MOX)
(Uirr : 208 kg)
Actinides
WASTE
U : 1.737 kg Pu : 0.085
Np : 0.0036 Am : 0.0140 Cm : 0.0078 FP : 118.42
Disposal
Pu
PUREX (UOX)
(U irr : 1476 kg)
FR (19%)
Pu
PUREX (MOX)
ADS (5.2%)
MA
PYRO (29AcN-71ZrN)
Pu
MA
MA
FP, HM losses
FP, HM losses
U nat : 13 561 kg
Enrichment
UOX Fuel 1 579 kg
MOX Fuel 236 kg
U dep : 11 757 kg
FR Fuel 106.2 kg
ADS Fuel 46.2 kg
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 29
Scheme 3c variant 1 Carbide reprocessed (PYRO) – TRU partitioning and homogeneous transmutation
Fuel Characteristics and Mass Flows (kg/TWhe)
GCFR
U, Pu, Am, Cm, Np
PYRO Reprocessing
PYRO
WASTE
U : 0.588 kg Pu : 0.161 kg
Np : 0.0009 kg Am : 0.0068 kg Cm : 0.0029 kg
FP : 86 kg
Disposal LLW
Pu : 161 kg Np : 0.9 kg Am : 6.8 kg Cm : 2.9 kg FP : 86 kg U : 588 kg
Cooling time : 1 year
U dep : 86 kg
CERCER FUEL (U,Pu)C ; SiC
845 kg
Cycle 3c var1 : all An recycled in a Gas Cooled FR
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 30
Complete Fuel cycles
HLW, ILW, LLW
include all waste
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 31
Complete fuel cycles : provide HLW, ILW AND LLW waste streams for
Partitioning plants 7 types
Fuel fabrication plants 7 types Encapsulation & Conditioning plants 7 types Front end flows : 2
types Unat, Uenriched, Udepleted Back-end facilities : 5 types
storage, decay storage and disposal Decommissioning waste for all plants Chemical toxicity Reactors : not direct waste producers 6 types
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 32
Partitioning plants (7 types)
P1 PUREX P2 UREX+ P3a PYRO metal fuel P3b PYRO nitride fuel P3c PYRO carbide fuel P4 Advanced PUREX P5 Fission products separation
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 33
Fuel fabrication plants (7 types)
FP1 Oreox FP2 Fission product targets FP3 Actinide targets FP4 Oxide fuel FP5 Nitride fuel FP6 Carbide particle fuel FP7 Metal fuel
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 34
Encapsulation plants (7 types)
E1 Spent fuel E2 Transmutation targets E3 Spallation targets E4 HLW E5 ILW E6 LLW E7 Metals
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 35
Front-end flows
U1 Residual uranium, mass flows U2 Residual uranium, possible options
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 36
Back-end facilities (5 types)
DS Decay storage (heat decay of Cs, Sr, …)
S Storage D1 Disposal of spent fuel D2 High heat load waste D3 Cooled waste
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 37
Other boxes
DW Decommissioning wastes CT Chemical Toxicity
Reactors (6 types) : no direct waste produced PWR Candu FR ADS GCFR LMFR
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 39
Integration path for all data via costs
After some iterations, choice of a basic integration approach and of a tool
1 table of unit costs: 89 costs over 5 categories : • General, reactors, fuels, reprocessing, waste disposal• Per cost : lower bound, avg, upper bound provide basis for
sensitivity analysis• Estimated from established costs when available and relative
comparisons elsewhere• All cost normalized to the service rendered, in TWHe
1 Excel sheet per fuel cycle flowchart (K. S. Lee) All process boxes deliver primary and secondary flows Flows characterized by mass, volume, activity, heat load and cost
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 40
Scheme 1a
- parameter Summary (mills/kWh) - calculated value Fuel cycle Reactor Total - value defined somewhere else Cost Natural U 0.62 PWR - cost Cost Conversion 0.10 Investment 25.16
Cost U enrichment 1.27 O&M 9.32Cost of storing Udepl 0.00Cost UOX fab 0.51Cost Int storage 0.62Cost Geo storage 0.62
Natural uraniumCost of fuel cycle 3.74 Cost of reactor 34.48 COE (mills/kWh) 38.22
Mass flow 20785Loss Factor 0CostU 30Cost Natural U 623552
Conversion Enrichment UOX fuel fabrication
Mass flow 20785 Mass flow in 20764 Mass flow in 2052Loss Factor 0.001 Loss factor 0.001 Loss factor 0.001CostUconv 5 UOX enrichment 4.90% Mass flow out 2050Cost Conversion 103925 Mass flow out 2052
CostUOXfab 250CostUenr 80 Cost UOX fab 513013SWU 15866Cost U enrichment 1269274
Depleted uranium
Mass 18712Enrichment 0.25%
CostUdepl 0Cost of storing Udepl 0
U Natural
Enrichment
U Depleted
UOX Fabrication
PWR
LLW, ILWDisposal
DISPOSALDisposal
S/F Storage
Conversion
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 41
- parameterNatural uranium - calculated value
- value defined somewhere elseMass flow 13602 - costCostU 30Cost Natural U 408050
Conversion
Mass flow in 13602 Depleted uraniumLoss factor 0.001Mass flow out 13588 Mass 12007
Enrichment 0.25%CostUconv 5Cost U conversion 68008 CostUdepl 0
Cost of storing Udepl0
Enriched uranium
Mass flow in 13588Loss factor 0.001UOX enrichment 4.20%Mass flow out 1581
CostUenr 80SWU 9901Cost U enrichment 792047
UOX fuel PWR MOX fuel FR MOX fuel
Mass flow in 1581 Mass flow in 235 Mass flow in 106Loss factor 0.001 Loss factor 0.001 Loss factor 0.001Mass flow out 1579 Mass flow out 234 Mass flow out 106
CostUOXfab 250 CostUOXfab 1100 CostFRMOXfab 1400Cost UOX fab 395207 Cost UOX fab 258021 Cost FR MOX fab 148408
Spent UOX fuel Spent PWR MOX fuel Spent FR MOX fuel
Mass flow total 1579 Mass flow total 234 Mass flow total 106Mass flow U 1477 Mass flow MOX 234 Mass flow U 106
CostUOXIntstor 60 CostMOXIntstor 60 CostMOXIntstor 60Cost Int storage 94755 Cost Int storage 14059.8 Cost Int storage 6354
UOX repro PWR MOX repro FR MOX repro
Mass flow in 1579 Mass flow in 234 Mass flow in 106Loss factor 0.001 Loss factor 0.001 Loss factor 0.001Mass Flow out 21.35 Mass Flow out 14.63 Mass Flow out 37.2Waste Mass flow out 1556 Waste Mass flow out 219 Waste Mass flow out 69
CostUOXrepro 800 CostMOXrepro 800 CostFRMOXrepro 2000Cost UOX repro 1263400 Cost MOX repro 187464 Cost FR MOX repro 211800
U Depleted
S/F Cooling
PWR (UOX) FR (MOX)
FR Fuel Fabrication
S/F Cooling
MOX Fabrication
PWR (MOX)
S/F Storage
LLW, ILW Disposal
U Natural
Enrichment
UOX Fabrication
Conversion
LLW, ILW Disposal
Scheme 3b upper left part
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 42
Spent UOX fuel Spent PWR MOX fuel Spent FR MOX fuel
Mass flow total 1579 Mass flow total 234 Mass flow total 106Mass flow U 1477 Mass flow MOX 234 Mass flow U 106
CostUOXIntstor 60 CostMOXIntstor 60 CostMOXIntstor 60Cost Int storage 94755 Cost Int storage 14059.8 Cost Int storage 6354
UOX repro PWR MOX repro FR MOX repro
Mass flow in 1579 Mass flow in 234 Mass flow in 106Loss factor 0.001 Loss factor 0.001 Loss factor 0.001Mass Flow out 21.35 Mass Flow out 14.63 Mass Flow out 37.2Waste Mass flow out 1556 Waste Mass flow out 219 Waste Mass flow out 69
CostUOXrepro 800 CostMOXrepro 800 CostFRMOXrepro 2000Cost UOX repro 1263400 Cost MOX repro 187464 Cost FR MOX repro 211800
Pu (19 kg)
Pu (12,9 kg) Pu (34,3 kg)
MA (2,35 kg) MA (1,73 kg) MA (2,90 kg)
LLW, ILW Disposal
HLW Disposal
S/F Cooling
PWR (UOX)
PUREX
S/F Cooling
PUREX
PWR (MOX)
S/F Storage
PUREX
Scheme 3b lower left part
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 44
Connections to NSC-WPFC-WGFS
The WGFS covers all spent fuel separation technologies (aqueous and pyro)
The WGFS has answered positively to our request of quantifying/estimating the composition and character of the separation products for ...
The new WP structure of the Nuclear Science Committee of NEA, Has installed a Workimg Party for scientific issues of the Fuel
Cycle WPFC• That has set up a Working Group on Flowsheet Studies
WGFS
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 45
Help from NSC-WPFC-WGFS
Flowsheets to be studied by WGFS Oxide :
• Purex standard, extended and advanced, Urex+2• Pyrox, Dimitrovgrad dry, fluoride, Criepi
Coated particle fuel Metallic Nitride Molten salt
Composition and volume by ton of reference fuel Recycle material HLW LLW ILW
... by end December 2004
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 46
Performance assessments of repositories (1)
2 Fuel cycle scenarios retained for detailed analysis 2a Pu mono-recycled in PWR 3cvar1 All An recycled in GCFR Contrast should be maximal, other scenarios analysed as trends
2 Fission product managements variants Cs and Sr cooldown 5, 50, 200 and 1000 years Orient cycle = maximal recycle of FP
Host rocks Clay Salt Granite (volunteeers are welcome) Tuff (volunteers are welcome)
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 47
Performance assesssments of repositories (2)
Study of normal operation Possibly loss of one major barrier
Based on publicly available repository PA UK NIREX CH NAGRA Opalinus Clay BE SAFIR Boom Clay FI TILA-99 Granite ...
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 51
Status of EG Impact as of today
All scenarios regarding the recycled material flows
are ready Qualitative and most quantative information
regarding losses is gathered Some quantîtative information is still missing,
mainly on losses from advanced reprocessing concepts
Support from NDC on advanced reprocessing concepts is imminent
8th IEM, Las Vegas 9 nov 2004 NDC/RWMC EG Impact 52
Conclusion
Performance assessments are outlined and under way Cost are available, with sizeable uncertainties Integration tool is ready Next meeting in Madrid, December 1st, should bring
together most (all ?) the pieces of the puzzle Final report is foreseen by summer 2005