ThEC Industrial View on Thorium October p. 1

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2 An industrial view on Thorium: Possibilities, Challenges and Paths forward Luc Van Den Durpel Vice President Strategic Analysis and Technology Prospective Corporate R&D ThEC 2013 Conference October 28 th October 31 st 2013 CERN, Geneva

3 Possibilities for Thorium use in nuclear energy systems p. 3

4 Why is Thorium that «modern» again? «It is neutronically exciting» As soon as you introduce fertile materials, e.g. Th, you need to balance the neutrons well 233 U can act as the «239 Pu» in thermal neutron spectrum reactors And can provide routes to synergies among thermal neutron spectrum reactors Provides higher conversion ratio routes in thermal neutron spectrum reactors Though, some 233 Pa- 233 U management issues in-core «It can, in the longer term, offer some advantages» Less MA-production Higher melting point & cooler fuel One oxidation state «It s not plutonium» Claims on proliferation risk advantages Provides an avenue to a «new nuclear» p. 4

5 «Generation-IV» There s a (re)new(ed) «hype» on thorium today But most proposals today on Th only address one family of strategies, i.e. «Thdedicated nuclear energy systems» Many can be classified as «Generation-X» (X 5) when full account is taken of fuel cycle developments required Pu and MA-management During the last two decades, Partitioning and Transmutation (P&T) was a strong driver of advanced fuel cycle R&D worldwide E.g. Pu/Th-option for Pu-management Nuclear energy sustainability E.g. India transitioning towards 233 U/Th-cycle p. 5

6 Socio-political consequences from this hype «We can accept nuclear energy as solution, as long as it is Th-based» Increasing debate and flawed discussions on the potential of thorium canibalising a true scientific-technological assessment of Th The debate is mostly or even solely driven by longer-term «Generation-IV/X» projections Scientifically-technologically correctness is required There will never be a «Th fuel cycle» without a (starting) complementarity with a U/Pu-cycle Any Th-use requires a fissile material to start with Any Th-fuel cycle requires reprocessing and recycling to make true use of 233 U and achieve the objectives The claimed benefits of «Th fuel cycle» will only be gradually achieved and will take a long time as well (>100 yrs) p. 6

7 Let s demystify the role of Thorium a little There are essentially three major families of scenarios envisaged for use of Th/ 233 U Complementary use of Th/ 233 U in U/Pu nuclear energy systems Possibility to use Th/ 233 U in LWRs, PHWRs and FRs in view of - Lengthening the cycle time in LWRs - Reducing the U nat /TWhe use, and/or - Providing multiple-recycling option for Pu, and/or - Replacement of DU in specific cases, and/or - Breed 233 U for future use in other reactor systems (Transition towards ) «Generation-III(+)» 100% Th/ 233 U-nuclear energy systems Th provides synergies between thermal spectrum reactors, e.g. LWRs + CANDUs/AHWRs as well as with FRs Th-dedicated «Generation-IV/X»-systems (X 5) «Generation-IV/X» longer-term options considering use of MSRs, ADSs, LFTRs, p. 7

8 Th-use in nuclear power demands a (LT) strategy why Th would bring value in a nuclear programme Forget the claims that, internationally, «Th-fuel optimised NPPs» would be available tomorrow, e.g. < 2030 There are today no classic argumentations driving in favour of th instead of U nat /Pu For an investor in an NPP, the international market offers reliable industrial solutions with international fuel cycle services in the U/Pu-cycle No additional risks introducing game-changing technologies to ensure competitive nuclear energy Only with a medium- to longer-term strategy, and addressing strategic issues, Th may become a viable option for consideration Th-fuel development and qualification in Gen-III(+) reactors takes time and transitioning from an initial UOX/MOX-core towards a (partial) Th-OX fueled core takes time as well Unless a government drives a large Th-fuel and reactor (R&D-)programme with a long-term vision, Th-use in nuclear power will occur Progressively in Gen-III(+) reactors, potentially preparing Gen-IV and/or Gen-X options Providing the answer to specific challenges which are primarily of fuel cycle nature Ensuring that the Th-containing fuel is well complementary with the U/Pu-cycle and offering additional flexibility to NPP-operators and countries p. 8

9 Indicative timeline for U/Pu/Th-use in nuclear energy systems HTR ADS / MSR/LTFR 233 U / Th UTh-OX AHWR 233 U Th Th-Blanket F(B)R FR-MOX U-Blanket Pu Pu UOX Pu MOX Pu MOX Pu ALWR LWR U URT URT URT PHWR Today p. 9

10 As nuclear will grow there might be some concerns Temporary imbalances of supply/demand for front-end services, specifically U nat availability, may lead to higher and more volatile fuel prices during the period Perception of temporary scarcity due to possible imbalance U nat supply/demand especially in light of rapidly growing regional NPP-parks with additional effect from U-traders in a single-product market NPP s trend towards technical lifetimes (well) beyond 60 years Investors need to be assured that fuel availability is not an issue for their investment over long time horizons Today s LWR-designs will be operating well into the 22 nd century!! As such, fuel cycle flexibility is becoming increasingly important Planning actions towards higher fuel cycle flexibility include In the short and medium-term fuel delivery contracts (time-period, multiple providers, ) In the medium- to longer-term technical fuel and fuel cycle flexibility, i.e. having qualified fuels with fissile/fertile content U-Pu, 30%-100% MOX, U-Th, Pu-Th, 233 U-Th according to market and technological developments In addition, new NPPs, i.e. specifically allowing «multi-recycling Pu» in LWRs and ultimately FRs provide better use of natural resources while also potentially reducing amount of ultimate radioactive waste p. 10

11 Challenges ahead p. 11

12 What are the drivers to use Thorium in nuclear power especially, and ideally, at larger scale in due time? What are the new market -conditions for Th-use compared to the past? Nuclear power is a hugely capital-intensive industry with thus, inherently, technology lockin behaviour And do not forget fuel cyccle technlogies development and strategies! Th/ 233 U involves multiple issues in a 100% Th/ 233 U fuel cycle, i.e.: Fissile material balance for start-up Recycling and especially refabrication issues with 232 U Proliferation risk assessment is not univocally in favour only If there wouldn t be new market conditions, one could easily remain with Th on paperlevel if not driven by a governmental strategy as the switching costs from U/Pu to Th/ 233 U for nuclear industry are very important or even huge Are there any new drivers today that would facilitate progressive introduction of Th? And if so, ideally addressing a large part of the nuclear power park worldwide, i.e. addressing LWR fuel cycle? p. 12

13 Conditions to consider Th in LWR-based energy systems? Are there any improvement avenues in U/Pu-cycle where Th provides added value? Lengthening the cycle time in LWRs Reducing the U nat /TWhe use, and/or Providing additional multiple-recycling option for Pu, and/or Replacement of burnable poisson in specific cases But Fuel cycle impacts especially in recycling schemes Any consideration of Th-use needs to be progressive Keep as long as possible the «thorified» fuel separate from the U/Pu-cycle This means How? As long as possible, keep both fuel cycles separated Couple U/Pu and Th/ 233 U neutronically though not physically nor chemically for as long as possible until there might be a market to go towards «Th fuel cycle» p. 13

14 An alternative scheme among many considerable 233 U / Th Th UTh-OX AHWR 233 U Th-Blanket F(B)R PuThOX Pu Pu FR-MOX U-Blanket Pu UOX MOX ALWR UOX Pu MOX Pu MOX Pu LWR U URT URT? URT? PHWR Today p. 14

15 There are multiple paths before embarking into «Th-cycle»: some provide complementarity with U/Pu-cycle already in medium-term Fraction of Th in U/Th or Pu/Th fuel (%) 100 «Th/ 233 U-cycle» with Th-optimised reactor concepts Pu/Th options AHWR (India) LWRs/CANDUs U/Th options towards U nat /TWhe reduction MSR LFTR Objectives: U nat /TWhe reduction through in-core 233 U breeding and recycling Level of Th-content important for potential in reducing U nat /Twhe though demanding MEU for high Th-contents 50 Objectives: 5 10% Pu/th U nat /TWhe reduction through in-core 233 U breeding and recycling Multi-recycling of Pu (from used MOX) in LWRs % Pu/th Pu-burning while breeding 233 U in transition scenarios High BU options with SiC cladding for once-burn-disposal 10 Th as additive Objectives: BU and cycle length extension Reduction/Replacement of Gd as burnable poison Core power flattening LWRs / CANDUs p. 15

16 Some take-aways from AREVA s assessment of Th-options in LWRs Based on EPR TM -design evolutionary fuel options Envelope of evolutionary Th-use potential One can introduce beneficially Th in LWRs while keeping U/Pu and Th/ 233 U-vector as long as possible separated Some 20 to 50% of energy provided by 233 U Most options require reprocessing to ensure achievement of objectives Though, given stable 233 U, reprocessing may be delayed Reduction by % of U nat /TWhe in recycling schemes An improved Pu-balance in UOX and MOX for multi-recycling of Pu Reduction in enrichment needs Reduced MA-production p. 16

17 AREVA and Thorium: expertise and experience dating from the 1970s Thorium is not new for AREVA AREVA holds inventory of 2450 tth as Th-nitrate in France from former mining operations (Madagascar) and AREVA developed the appropriate technological solutions for its proper management (processing, handling, interim storage) AREVA researched and (co-)fabricated Th-fuels for PHWRs, HTRs, and LWRs 1970s BWR Lingen irradiation of 2.5%-Pu/Th pellets (20 GWd/tHM) 1980s collaborative program on Th-fuel for PWRs s PWR Obrigheim UPu/Th irradiation (up to 37 GWd/tHM) - PIE indicated no issues Sol-gel, powder metallurgy and impregnation fabrication methods were tested and no major issues up to 30% Pu were encountered though demanding modified process parameters Ceramic lab(s) still available and equipped for Th-fuel R&D-programme(s) p. 17

18 Paths forward p. 18

19 Thorium can have its place in a growing nuclear energy future As nuclear energy is a prime contributor to address climate change and energy sustainability objectives worldwide A progressive and U/Pu-complementary introduction of Thorium is conditional to any Th-use in the future Any introduction of Th needs to be assessed industrially to ensure technicaleconomic effective and efficient paths forward for such Th-use Given the overall worldwide developments related to thorium, both in the nuclear energy field as in the rare-earth market AREVA and SOLVAY join their know-how to add value to thorium s entire life cycle p. 19

20 AREVA and SOLVAY s provide holistic Th-management RE-mining RE-ore processing REO separation and purification REO processing into products Thresidues Thresidues Interim Storage Thresidues Separation and Purification of Th LT Interim Storage Th Valorisation as Th-fuel in nuclear power Other applications of Th p. 20

21 AREVA-SOLVAY «Thorium Valorisation» Agreement AREVA and Solvay embarked since 2013 in a collaborative programme towards Thorium valorisation Both companies together master the complete set of Thorium valorisation routes in the short- to longer-term with clear synergies ensuring Thorium valorisation services also to be provided to third parties. The collaborative programme encompasses Resolving the Th-residues issues arising from certain Rare Earth processing in the past and now Providing an industrially robust valorisation argumentation focused on Thorium valorisation in nuclear power in the medium-term Ensuring best-practice interim management options for Thorium awaiting this Thorium valorisation in the medium-term An R&D-programme focused on medium-term Thorium valorisation in nuclear power is set-up with international R&D-partners geared towards first phase of fueldevelopment with irradiation by 2020 p. 21

22 Synthesis of AREVA-SOLVAY s R&D-programme on Th-valorisation in nuclear energy Phase 0 Phase 1a Phase 1b Phase 2 Phase 3 Phase 4 Selection of NPPirradiation and licensing of irradiation Downselection of Th fuel cycle strategies and fuel fab development focus Decision on Th-fuel development Detailing fuel cycle strategies with international partners R&D international consortium Preparing labs Licensed Irradiation in NPP start Decision on Lead Test FA irradiation «There is clear scope for Thuse in future nuclear power and R&D-programme to be strengthened» Scoping Analysis of Th-options Reactor Physics studies (LWR, PHWR, FR) PhDs Techno and Patent Watch International Projects involvement Know-How transfer Fuel Fab development and testing Experimental R&D Programme NPP Segmented Rod irradiation to high BU and PIE Lead Test FA Irradiation Qualified Th-fuel development p. 22

23 In Summary p. 23

24 Concluding observations Please, demistify the «Th fuel cycle» story and claims Th-dedicated «Generation-IV/X» systems won t make it: Without an initial long period of complementarity with U/Pu-cycle in Gen-III(+) and IV systems Without a government long-term vision spurring their development Is there a clear market for U/Th and Pu/Th-fuels in the short-term? In the medium-term: possibly depending on the international nuclear energy systems development and the requirement for fissile/fertile materials management synergistically intra-nuclear and inter-regionally Transition, if desired to go towards «100% Th», will take a time, i.e. decades at least AREVA and SOLVAY are investigating Th-fuel options as complement to U/Pu-cycle in an international context and addressing a holistic Thorium management providing industrial solutions to those requiring and considering valorisation of thorium both in Rare Earth as in nuclear energy market AREVA and Solvay welcome collaboration with R&D-organisations and other companies p. 24

25 Thank you p. 25