Status of SNF Pyro Reprocessing RIAR, Dimitrovgrad, Russia

1. SSC Research Institute of Atomic Reactors. RUSSIA Status of SNF Pyro ReprocessingRIAR, Dimitrovgrad, Russia Mikhail Kormilitsyn Research Institute of Atomic Reactors (RIAR) Radiochemical Complex

2. RIAR General Goal Closing of FC Radionuclide Productions PIE Research Reactors Fundamental Studies MA recycling Advanced Fuel development and testing Fuel Supply of BOR-60/MBIR R&D for MSR Fuel Cycle RAW Treatment Demo of Closed Fuel Cycle

3. New Generation Technological Package“Pyro-Chemistry for CFC” Universal technological platform for decisions in the field of Closed Fuel Cycle of Nuclear Power: • No limitation for: • fuel types (oxides, nitrides, metal, carbides, cermet, MSR, IMF) • burn up, • cooling time • No limitation for requirements of decontamination factor (DF up to 106)

4. New Generation Technological Package“Pyro-Chemistry for CFC” • The Base System – Molten chlorides • The Base processes • Dissolution of initial SNF ( chlorination or anodic dissolution) • Electrolysis on solid and/or liquid cathodes • Precipitation • Purification of the melt • Option – Technology of fluoride volatility • Option – Partitioning in fluoride melt • Option – chemistry and technology of molten fluoride fuel of MSR

5. R&D on SNF Pyro Reprocessing in a World • Oxide SNF reprocessing into Oxide – RIAR (Russia), JNC/JAEA (Japan) • Oxide SNF reprocessing into Metallic – CRIEPI (Japan), KAERI (Korea) • Nitride SNF reprocessing – JAERI/JAEA (Japan), RIAR (Russia) • Metallic SNF reprocessing – INL, ANL (US), CRIEPI (Japan), RIAR (Russia) • SNF metallization – KAERI (Korea), RIAR (Russia) • HLW partitioning in molten salts – CRIEPI (Japan), RIAR (Russia), KAERI (Korea), CEA (France), ITU (EU) • Fluoride volatility processes – CRIEPI, Hitachi/TEPCO (Japan), Kurchatov Inst., RIAR (Russia), INR (Czech. Rep.) • MSR Fuel Cycle – RIAR, Kurchatov Inst., CNRS (France), Institute for Applied Physics, Shanghai (China) • Other application

6. RIARExperience

7. RIAR activities in the field of CFC • Since 1964 RIAR has been pursuing large-scale investigations in the following research lines: • Pyrochemical production technology of vi-pack U and MOX fuel • Pyrochemical reprocessing of SNF from nuclear reactors of various types. • Fluoride volatility reprocessing of SNF

8. Milestones of Experience in Closed Fuel Cycle • Pyro R&D- from early 1960-s • Demo of fluoride volatility reprocessing – 1970s • Pilot facility for pyro/vi-pack MOX fuel production for fast reactor – from late 1970-s • BOR-60 full scale fuel supplying only on the base of own RIAR pyro/vi-pack fuel production facilities – from 1980 • Pyro reprocessing experience – from 1991 • Study on transmutation cycle, nitride fuels and others – from 1992 • Start of industrial implementation of pyro/vi-pack MOX technology – 2012 • Start of so called “high density” FR SNF (nitride, metal) - 2010 • Creation of “Poly-functional Radiochemical Complex” (PRC) -2010-2017

9. RIAR experience in reprocessing of spent fuel of the BOR-60 and BN-350 reactors 9

10. Basic research of the molten salt systems allowed for the development of technological processes for production of granulated U and Pu dioxides and MOX. A distinctive feature of the Pyro technology is a possibility to perform all the deposit production operations in one apparatus - a chlorinator-electrolyzer Pyrochemical reprocessing consists of the following main stages Dissolution of initial products or spent nuclear fuel in molten salts Recovery of crystaline Pu dioxide or electrolytic MOX from the melt Processing of the cathode deposit and production of vi-pack Dimitrovgrad Dry Process (DDP) – MOX Fuel Pyro processing

11. Production and testingof vi-pack MOX fuel

12. Na3PO4 Cathode (pyrographite) Ar (Cl2) Cl2+O2+Ar Cl2+O2+Ar Cl2 Cathode Stirrer Stirrer Stirrer pyrographite bath, NaCl - KCl O2 UO22+ UO2 + NpO2 MA,REE UO2 Pu4+ Pu4+ Cl- UO22+ PuO22+ UO22+ UO22+ NpO2+ UO2 PuO2 PuO2 (MA,REE) RW4 Fuel chlorination 700 оС Preliminary electrolysis 680 оС Precipitation crystallization 680 оС Electrolysis-additional 700 оС Melt purification 700 оС Ar (Cl2) UO2 + NpO2 UO22+ NpO2+ Preliminary electrolysis 630 оС + + + + + DDP MOXPuO2 flow sheet Na3PO4 Cl2+O2+Ar Cathode (pyrographite) Cl2 Cl2+O2+Ar Cathode Stirrer Stirrer pyrographite bath, NaCl -2CsCl MOX MOX MA,REE Pu4+ Cl- UO22+ UO22+ UO22+ PuO2+ PuO2+ UO2 PuO2 (MA,REE) RW4 Main MOX electrolysis 630 оС Fuel chlorination 650 оС Electrolysis-additional 630оС Melt purification 6500 оС DDP MOXMOX flow sheet

13. MOX-MOX Reprocessing 2000Year MOX - 3 200 g Pu content - 10 %wt. 2004 Year MOX - 3 400 g Pu content - 33,5 %wt.

14. Pyro HLW treatment Na3PO4 Radioactive Cs Salt purification Salt residue Pyroreprocessing NaCl CsCl Fission products NdPO4CePO4 Phosphates * - TOSHIBA estimation for DDP

15. Vitrification of HLW from pyro process

16. Ceramization of HLW arising from pyro process

17. Since 1992 Dry technologies Oxide fuel with MA Vi-pack Integrated disposition on the same site with the reactor TA Transmutation of Actinides RIAR R&D PROGRAM DOVITA

19. Experience in DOVITA Program • Pyrochemical technology of adding Np into oxide fuel (5-20%) has been developed • Performance of vi-pack fuel with (U,Np)O2fuel has been validated experimentally to ~20% burnup in BOR-60 • No evidence of significant difference in performance of fuel rods with (U,Np)O2fuelcompared with UO2or MOXfuel rods has been noticed • Pyrochemical process of codeposition of Am with MOX fuel (2-4%) has been developed • Methods of Am/REE separation in melts has been tested • Special vi-pack targets containing Am oxide with UO2 or inert matrix have been developed • Transmutation of Np, Am, Cm is being studied in BOR-60 Irradiated (U,Np)O2 fuel,19% burn-up

20. 1992 Dry technologies Oxide fuel with MA Vi-pack Integrated disposition same site with the reactor TA Transmutation of Actinides New times consideration:DOVITA DOVITA-2 2007+ • Dry technologies • On-site reprocessing • Various type of fuel with MA • Integration of MA recycling into FR Closed Fuel Cycle • TA - Transmutation of Actinides

21. DOVITA-2 DOVITA-1

22. Current R&D

23. In the Frame of Federal Target Program For the First Time in a World – pyrochemical reprocessing of FBR spent U-Pu nitride fuel and metal fuel ~ 0,6 kg SF 2 Cd ingots for fabrication of fuel Oxide concentrate FP for wastes preparation

24. Experimental Tests of Spent Nitride Fuel Reprocessing Methods The empty pies of cladding after anodic dissolution of nitride SNF in chloride melt The sample of fluoride-phosphate glass with real immobilized FPs after reprocessing

25. 100% PuO2 Pyro Pellets PuO2 Pellets Characteristics PuO2 Pellets (3LiCl-2KCl, T=450oC) PuO2 Pellets (NaCl-2CsCl, T=550oC)

26. 80%UO2 + 20%PuO2 MOX Pyro Pellets MOX Pellets Characteristics *Reshetnikov Ph.G. and et al. Working out, production and operation of fuel rods of power reactors-M:.Energoizdat, 1995-320p.

27. Content, wt% Unpickled pellet Pickled pellet μm Pyro MOX pellets (80%UO2 + 20%PuO2) Microstructure of MOX pellets EPMA Solubility test in 8M HNO3 at 95-96оC , duration – 10 hrs.

28. Fuel pin #TM0-01 with pyro MOX pellets Dismountable BOR-60 FAs

29. Fundamental Studies Curium containing salt for spectroscopy studies NaCl-2CsCl-CmCl3(0.115mol/kg)

30. Spectrum of curium-containing melt underatmosphere of Ar-HCl-H2O Cm3+ CmO+ Am3+ NaCl-2CsCl-CmCl3(0.115mol/kg) 750oC log(P2HCl/PH2O)=-7.14

31. RE Oxygen pump CE Gas-supply tube Oxygen sensor Cavity from optical quartz Synchronized potentiometric titration by oxygen pump and spectroscopy

32. MA and FP Partitioning Ga cathod

33. Experimental Facilities till 2020

34. CFC Pyro technology for International RIAR-based Center of Excellence RIAR Site Post Irradiation Examination electricity Heat power radionuclides Post Irradiation complex R&D on Reprocessing and Refabrication of Advanced Fuels MBIR MOX or other fuel RadioWaste complex Vi-pack Вибро RAW Отходы на хранение MOX Production Facility Radiochemical Complex Chemical-Technological complex Refabricated Fuel Pyro Пиро RIAR Radiochemical Complex

35. Federal Tasks-oriented Program “New Generation Nuclear Power Technologies” • Large Poly-functional Radiochemical Complex (PRC) - 2017 • Molten salt Reprocessing Facility (1st hot cell line) • capacity – up to 1-2 tons of FR SNF per Year (fuel type: oxide, nitride, metallic, IMF) • Advanced water-technology Facility, (2nd hot cell line) • capacity – up to 1-2 tons kg of SNF per Year • New Lab for Experimental and Innovative Fuel Production – 2010-1017 (incl. Fuel and Targets with MA) • New facility for HLW treatment • Demonstration of Closing Fuel Cycle • Testing and Demonstration of Closing FR Fuel Cycle for MA • Develop the full scale Design of Industrial plants for FR SNF Reprocessing

36. List of Advanced R&D for PRC • Testing of prototypes of technological equipment • Development and testing of automatic and robotics systems • Comparative FS for different technologies • Advanced thermo-chemical decladding technologies • Voloxidation • Pyrochemical molten salt technologies • MOX fuel • Mixed Nitrides • Metallic • IMF, MSR • Remote control fabrication technologies • Vi-pack • Pelletizing • Metallic • RAW treatment • Vitrification • Ceramization

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38. THANK YOU FOR ATTENTION! RIAR Radiochemical Complex