8th iem, las vegas 9 nov 2004 ndc/rwmc eg impact 1 expert group on impact of advanced nuclear fuel...

8th IEM, Las Vegas 9 nov 2004NDC/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


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.


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


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


Complete Fuel cycles

HLW, ILW, LLW

include all waste


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


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


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


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


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


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)


UOX reprocessed (UREX) Pu, Np once cycling in MOX

HLW, ILW, LLW MOX fuels

N°1d PWR (UOX) CANDU


UOX reprocessed (OREOX) HLW, ILW, LLW UOX fuels


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


Partially closed fuel cycle


Nature of wastes

N°2a PWR (UOX) PWR (MOX-EU)


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


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


Fully closed fuel cycle


Nature of wastes

N°3a PWR (UOX) FR (metal)


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)



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)


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


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


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


Complete Fuel cycles

HLW, ILW, LLW

include all waste


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


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


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


Encapsulation plants (7 types)

E1 Spent fuel E2 Transmutation targets E3 Spallation targets E4 HLW E5 ILW E6 LLW E7 Metals


Front-end flows

U1 Residual uranium, mass flows U2 Residual uranium, possible options


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


Other boxes

DW Decommissioning wastes CT Chemical Toxicity

Reactors (6 types) : no direct waste produced PWR Candu FR ADS GCFR LMFR


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


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 250

CostUenr 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


- parameterNatural uranium - calculated value

- value defined somewhere elseMass flow 13602 - costCostU 30

Cost Natural U 408050

Conversion

Mass flow in 13602 Depleted uraniumLoss factor 0.001Mass flow out 13588 Mass 12007

Enrichment 0.25%CostUconv 5

Cost 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 80

SWU 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 1400

Cost 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 60

Cost 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 2000

Cost 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


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


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


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


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)


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 ...


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


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

8th iem, las vegas 9 nov 2004 ndc/rwmc eg impact 1 expert group on impact of advanced nuclear fuel...

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