13th GIF-IAEA Interface Meeting IAEA Headquarters, Vienna. 18-19 March 2019 GIF MSR systemDevelopment Status of Presented by Victor Ignatiev, RF [email protected] Status of MSR development 1 Different Reactor Concepts using Molten Salt are Discussed at GIF MSR pSSC Meetings • Within the GIF, research is performed on the MSR concepts, under the MOU signed by Australia, Euratom, France, Russian Federation, Switzerland and USA. • China, Canada, Korea, and Japan contribute as observers • Two fast spectrum MSR concepts are being studied, large power units based on homogeneous core with liquid fluoride-salt circulating fuel: MSFR design in France, Euratom and Switzerland as well as MOSART concept in the Russian Federation. R&D studies are on-going in order to verify that fast spectrum MSR systems satisfy the goals of Gen-IV reactors in terms of sustainability, non-proliferation, safety and waste management • The US is focused on liquid fueled MCFR (Molten Chloride salt Fast Reactor) as well as some other solid (FHR) and liquid fuel fluoride based designs • China and Canada, as observer in the pSSC of the MSR, are working on thorium - uranium liquid fuel fluoride salt designs, respectively TMSR and IMSR • 27rd GIF MSR pSSC meeting, was held at ANSTO (Australia) in March 2019 Status of MSR development 2 Status of expressions of interest rd pSSC Members Observers 27 GIF MSR pSSC meeting, ANSTO Canadian 10-15 March 2019 Consortium • Tuesday Australia Euratom France Russia US Switzerland China Japan Korea • Wednesday TEI CNL • Thursday RSWG Workshop • Friday ANSTO Technical Tour L. Edwards Materials X X X X X Salt O. Bennes X X X X X X X properties System J. Krepel X X X X X X X X Integration Most of the MSR pSSC members and observers have expressed their interest in the different PAs. Interest among PAs is quite “balanced” Observers should also join the SA Collaborations: Europe • Institutional projects with Direct funding - Gen IV policy support to EU commitments - Member states support • EU HORIZON2020 project (Indirect funds) - SAMOFAR project (ends 08/2018) - SAMOSAFER from 1/10/2019 (4 year project granted by EU) • Collaboration agreements with Member States - Netherlands – TUD, NRG (SALIENT01 irradiation - ~3M€) - Fuel preparation of SALIENT03 irradiation (followed by PIE) - Italy, Czech Rep., France, Slovakia • Collaboration agreements with International partners - US (I-NERI) - CNSC - Terrestrial Energy (Q-A work) MSR Activities at JRC • Synthesis of An-fluoride salts • Physico-chemical properties investigation • Thermodynamic Database of F- salts • Pyrochemical reprocessing of the fuel salt • PIE of fuels Status of MSR development 8 Czech activities in 2018 – 2019 • The main activities in the period from last pSSC MSR meeting to present days were focused on the preparation of the future measurement of the FLIBE neutronic parameters at the temperature range between 500 °C to 750 °C. • To realize these measurement at LR-0 experimental reactor, the new inserted zone with hot liquid FLIBE salt was calculated, predesigned and is now ready for manufacture. The new zone will be significantly bigger than the previous zone used for the measurement at room temperature. The zone will be preheated outside the reactor, then placed into insulation case and finally put into the reactor for measurement. • The other activities related to the development of Czech MSR program continued in agreement with the Czech national project on MSR technology development. These activities cover the FLIBE loop program (change of gaskets in loop flanges, preparation of the ŠKODA pump for the installation in the loop etc.), blade design optimizations of the ŠKODA impeller, continuation of the electrochemical studies of An/FP separation from fluoride salts and continuation of the long-term MONICR corrosion experiments in FLIBE. • Moreover, in the frame of collaboration between the Research Centre Řež and NRG Petten related to the irradiation experiments, both the MONICR samples for irradiation and the capsules of FLIBE salt with UF4 and ThF4 were prepared in Řež and now they are ready for shipment to Petten. Irradiation tests NRG Petten • SALIENT-01: • Gamma irradiation of fresh salt • 78LiF-22ThF4 in graphite crucibles samples • 12 out of 18 cycles completed (end of irradiation: September 2019) (LiF, BeF2, UF4, ThF4, 71.7LiF-16BeF2- • Preparations for post-irradiation examination are underway: 12.3UF4) • Gamma spectrometry • Radiolytic gas production: • Fission gas release by puncturing / mass spectrometry • SEM/WDS: Noble metal particle size, salt-graphite interaction, pressure vs. dose FP diffusion and vaporization-condensation • Sample synthesis and fabrication finished at research Center Rez • Start of irradiation scheduled Q3 2019 • SALIENT-03: • Design completed: • 75LiF-18.7ThF4-6UFx-0.3PuF3 in welded Hastelloy N / GH3535 capsules • Electric heaters, to avoid radiolysis • In-pile monitoring of pressure and redox potential • Projected start of irradiation: Q4 2019 Progress in Italy 500W No fan 500W No fan 2018 Collaborations in Russia • Institutional projects with Direct funding - Gen IV policy support to RF commitments • 2018 Rosatom MSR related Awards: KI, VNIITF, VNIINM, MCC, OKBM, NIKIET 1. R&D needs for closure of the nuclear fuel cycle for all actinides with MSR at MCC site 2. Development of the methods for actinides fluorides production as applied to MSR 3. Conceptual development of the fast U-Pu MSR • Collaboration agreements with International partners - EU (SAMOFAR - KI) - SINAP (China) 1. Key physical & chemical properties for different coolant compositions; 2. Combined materials compatibility & salt chemistry control; 3. Development and experiments with component molten salt test facilities 2018 DOE-NE Industry Awards • Modeling and Optimization of Flow and Heat Transfer in Reactor Components for Molten Chloride Salt Fast Reactor Application • Elysium Industries USA - $3,200,000 • Fluorination of Lithium Fluoride-Beryllium Fluoride Molten Salt Processing • Flibe Energy & PNNL - $2,627,482 • in situ Measurement and Validation of Uranium Molten Salt Properties at Operationally Relevant Temperatures • University of Connecticut (CFA-18-15065) - $799,979 • Development of an MC&A toolbox for liquid- fueled molten salt reactors with online reprocessing • University of Tennessee (CFA-18-15061) - $799,207 • Determination of Molecular Structure and Dynamics of Molten Salts by Advanced Neutron and X-ray Scattering Measurements and Computer Modeling • MIT (CFA-18-15093)- $800,000 • Corrosion Testing of New Alloys and Accompanying On-Line Redox Measurements in ORNL FLiNaK and FLiBe Molten Salt Flow Loops • Georgia Institute of Technology (CFA-18-14977) - $800,000 10 UNF infrastructure in Russia Facilities of Test Demonstration Centre being built at the site of the Mining and Chemical Combine after 2020 will start reprocessing of UNF from VVER-1000, providing a recovered fissile materials for recycling in thermal and fast reactors. TDC will become the reference basis for the large-scale RT-2 plant, which will provide an environmentally and economically acceptable system of VVER-1000/1200 UNF recycling both in Russia and abroad. VVER-1000 UNF – since 2016 UNF Centralized wet and dry storage facilities PuO2 Test Demonstration Centre for UNF reprocessing (commissioning in 2021) Underground research Partitioning and laboratory isotopes production (commissioning in 2024 ) Modernization of the HLW management infrastructure BN-800 MOX-fuel fabrication In accordance with today TDC flowsheet, the HLW, containing Am and Cm is the subject for vitrification Introduction of MOSART into nuclear power help to solve the problem of long-lived actinides Fuel salt, mole% LiF-BeF +1TRUF Used fuel Reprocessing Waste conditioning 2 3 Temperature, оС 620-720 ILW Core radius/height, m 1.4/2.8 VVER disposal ILW Core specific power, W/cm3 130 Container material HN80MTY alloy Fresh fuel U, Pu TRU Removal time for soluble FP, yr 1-3 Solvent, Feed Loading TRU/MA, Enrichment MSR mole % MA/TRU (EOL), t kg/yr & fabrication 73LiF-27BeF2 0.1 3.9 730/73 Uranium 73LiF-27BeF2 0.35 13.9 730/260 Production 73LiF-27BeF2 0.45 23.2 730/330 12 R&D work packages 1. Development of container material for fuel and intermediate circuit 2. Development of flowsheets for the preparation and processing of fuel salt 3. Development of structural materials for the fuel salt processing unit 4. Conducting physico-chemical studies 5. Development of analytical methods for monitoring the fuel salt and intermediate coolant 6. Justification of reactor safety 7. Development of technologies for auxiliary components and systems 8. Ensuring maintainability and organization of equipment maintenance 9. Development of control and measuring systems 10. Creation of an electrically heated mock up 11. Design development for the 10-50 MWt experimental reactor 12. Design development for a 2.4 GWt MOSART The construction of a large power MOSART is proposed to be preceded by the construction of 10 MWt test MOSART unit to demonstrate the control of the reactor and fuel salt management with its volatile and fission products with different TRU loadings for start up, transition to equilibrium, drain-out, shut down etc. 2019 Program plan for 2020 R&D needs Pre-conceptual Experimental 2025 studies of the infrastructure reactor plant and (radiation damage 2028 processing unit must tests and integral Design be performed to forced convection documentation of establish the MSR Development of salt loops) are the 10 MWt MSR 2033 viability