Fast Reactor Research in Rossendorf

Transcription

1 Fast Reactor Research in Rossendorf B. Merk Department of Reactor Safety at Institute of Resource Ecology Helmholtz-Zentrum Dresden-Rossendorf TWG-FR, Chicago 2012 Text optional: Institutsname Prof. Dr. Hans Mustermann Mitglied der Leibniz-Gemeinschaft

2 Content Liquid metal technologies Analytical solutions for ADS Core simulator for fast reactors Enhanced feedback coefficients Molten salt reactor for the phase out in Germany Seite 2/30

3 Liquid Metal Technology - Magnetohydrodynamics (MHD) Department Text optional: Institutsname Prof. Dr. Hans Mustermann Mitglied der Leibniz-Gemeinschaft

4 Instrumentation for Liquid Metal Flow flow meter based on phase change x-ray radio tomography, bubbles in liquid metal flow receiver coil1 emitter coil receiver coil2 induced currents channel wall z x y magnetic field rising argon bubbles in molten GaInSn 1500 cm³/s 500 cm³/s Priede et al., Meas. Sci. Technol. 22, (2011) Boden et al., EPM 2009, Dresden, Seite 4/30

5 Liquid Metal Heat Exchanger liquid metal intermediate heat exchanger attractive solution to prevent the possible contact of hot molten metal and water coolant adjustable heat exchange rate development and test of analog system for sodium currently under decommissioning new facility for the new XS measuremnt lab at updated elbe accelerator Seite 5/30

6 Project DRESDYN at HZDR DRESDYN: A European platform for Dynamo-experiments and thermohydraulic studies with liquid sodium Infrastructure project at HZDR ( ), existing budget ca. 23 M Precession driven Dynamo: 2 m diamter, 2 m height 6.3 m 3 Na Rotation with 10 Hz Precession with 1 Hz Rm ~ 200 Na pool-type experiment for CIFT demonstration, flowrate and ultrasonic measurements bubble entrainment, bubble detection, etc. Seite 6/30

7 A Solution for the Telegrapher s Equation with External Source: Application to YALINA Text optional: Institutsname Prof. Dr. Hans Mustermann Mitglied der Leibniz-Gemeinschaft

8 The YALINA-Booster facility subcritical assembly at the YALINA facility in Belarus x x fast neuton flux thermal neutron flux reference elem ent fast and thermal neutron flux reference element Fast zone: metallic U (90% enr.) + UO2 (36% enrich.) in lead matrix Thermal zone:uo2 (10% enr.) in polyethylene matrix Boron carbide and natural uranium rods to decouple the two zones Graphite reflector Experimental channels (4 fast zone, 3 thermal zone, 3 reflector) production XS nu * fission XS [cm -1 ] reference elem ent Seite 8/30

9 Analytical Solutions Comparison with Experiment previous one group P 1 solution two group diffusion solution with adopted source Publications: Derivation of 1 group P 1 and diffusion solution: Transport Theory and Stat. Physics 37(2008) Application: Il Nuovo Cimento B 125(2010) Integration of delayed neutron source: Nuclear Science and Engineering 161(2009) Nuclear Science and Engineering 163 (2009) Derivation of 2 group solution: Annals of Nuclear Energy 37(2010) Application: Progress in Nuclear Energy 58(2012) Overview: Sci. and Tech. of Nuclear Installations (2012) Derivation 2 region solution for GUINEVERE: Transport Theory and Statistical Physics (2012) Seite 9/30

10 Extension of the DYN3D code towards fast reactor applications Text optional: Institutsname Prof. Dr. Hans Mustermann Mitglied der Leibniz-Gemeinschaft

11 Our Strategic DYN3D Project FREYA some extensions for fast reactor transients needed DYN3D Tool for steady state and transient core calculations of GenIV reactor systems ESFR EBR-II benchmark Ready for application Seite 11/30 ready to be validated for steady state coupling with TRANSURANUS VHTR benchmark

12 The DYN3D Code Neutronics multigroup solver tested and validated up to 47 groups SP3 and diffusion on trinagular mesh validation phase DYN3D test calculations for ESFR Thermal hydraulics Sodium thermal hydraulics in testing phase Fuel rod model A PhD student has started Sept 2010 (coupling with TRANSURANUS) incorporation of Structural feedback effects for EBR-II benchmark Validation ~ 24 pm in FREYA for validation for LFR SFR: IAEA CRP on EBR-II SFR: proposal for STC with IPPE in negotiation Seite 12/30

13 SFR analysis approach (DYN3D validation program) Create few-group XS with Serpent Monte-Carlo code neutron transport code Use few-group XS (24 groups) in the DYN3D code 3D multi-group nodal diffusion code CSD DSD Full core Monte-Carlo vs. DYN3D diffusion Serpent DYN3D Difference, Serpent vs. DYN3D K-eff pcm CVR, pcm pcm DC, pcm/k % CR worth, pcm pcm Outer Fuel Sub-Assembly Radial Reflector Inner Fuel Sub-Assembly CSD = Control and Shutdown Device; DSD = Diverse Shutdown Device Relative difference in radial power, % Seite 13/30

14 IAEA CRP on EBR-II Benchmark There will be two major contributions from Germany from the SIMMER group a coordinated German contribution using updated LWR tools for coupled calculations ATHLET System code DYN3D Core simulator SUBCHANFLOW Subchannel analysis code Seite 14/30

15 Use of Moderating Material to Improve the Safety Characteristics in Fast Reactors Text optional: Institutsname Prof. Dr. Hans Mustermann Mitglied der Leibniz-Gemeinschaft

16 Enhanced Feedback Coefficients Neutron flux per unit lethargy (1/cm²/s/eV) Insertion of fine distributed moderating material: Hydrogen bearing metal compound Significant low energy tail formed in the spectrum Ideally located in the spacer wire ZrH or better YH for increased thermal stability MOXRGP B 4 C ZrH 2 ZrB Neutron Energy (ev) Merk, Weiß, Annals of Nuclear Energy 38,5, (2011), Merk, Weiß, Annals of Nuclear Energy 38,11 (2011) Merk, Fridman, Kliem, Weiß, Nuclear Sc. and Eng. 171 (2012) Seite 16/30

17 Existing Work for SFR change reactivity coeff. [%] reference Doppler coefficient Coolant coefficient wire spacer Significant improvement of Doppler effect Reduction of positive coolant effect Strong reduction of sodium void effect Gain in sodium void is tranferable to full core - loss in criticality - slightly reduced breeding performance Conservation of fuel assembly geometry No hot spots like for moderation rods Uniform burnup distribution Nearly no influence on transmutation performance Possibility for compensation of MA influence on safety in transmutation cores Seite 17/30

18 Neutron Flux Spectrum for LBFR Neutron flux spectrum in the fuel assembly of CDT fuel assembly with and without moderating material hard neutron spectrum due to lead-bismuth coolant weak Doppler effect due to hard spectrum Neutron Flux Spectrum 1E16 1E15 1E14 1E13 1E12 1E11 1E10 1E9 1E8 1E ref pin YH Y2H U radiative capture corss section (barn) Neutron Energy (ev) Seite 18/30

19 Improved Feedback Effects Fuel Doppler effect for a heat up of ±200 C Coolant effect for a heat up of ±50 C Reference case Cases for YH and Y 2 H with moderating material per fuel rod Strong improvement of el and coolant temperature effect due to use of moderating material Changes in reactivity effect [%] pin YHwire YH 0.5 wire Doppler effect T+200 Doppler effect T-200 Coolant effect T+50 Coolant effect T Seite 19/30

20 GUINEVERE at VENUS-F GUINEVERE: Generator of Uninterrupted Intense NEutrons at the lead VEnus Reactor zero power experiments in a lead matrix for accelerator driven system critical system Seite 20/30

21 Neutron Flux Spectrum Neutron flux spectrum in the fuel assembly with and without moderating material extremely hard neutron spectrum due to: lead matrix metal fuel Neutron flux per unit lethargy (1/cm²/s) GIUN ref GUIN ZrH GUIN ZrH II SFR UOX SFR ZrH Neutron Energy (ev) U Radiative capture corss section (barn) Seite 21/30

22 The Molten Salt Fast Reactor as Transmutation System in the View of the Nuclear Phase Out Tuyen Vu Hervé Rouch, 2012 Text optional: Institutsname Prof. Dr. Hans Mustermann Mitglied der Leibniz-Gemeinschaft

23 Sorry for the sometimes very German view but for us there is no way to ignore the NUCLEAR PHASE OUT DECISSION when we want to have a future in nuclear research in Germany Text optional: Institutsname Prof. Dr. Hans Mustermann Mitglied der Leibniz-Gemeinschaft

24 Advantages for the MSFR absence of solid fuel no solid fuel production no multi recycling strong negative feedback due to coincidence of fuel and coolant no cycle time at all due to online reprocessing no excess reactivity required due to online refuelling TRUs stay in the reactor no transports required reprocessing losses (fission products) stay in the system no TRU losses to final disposal stream possibility of successive replacement of fissile component for solving the last transmuter problem Seite 24/30

25 Calculation Flow using PYTHON Script Calculation flow for the calculation of a molten salt reactor with online salt cleanup using HELIOS 1.10 expert input re-distribution of materials pre-processor user input post-processor AURORA HELIOS ZENITH SKRIPT re-feeding material output isotopes converged only printed isotopes Intensive use of the power of the post processing tool ZENITH of the HELIOS package Seite 25/30

26 Twofold Lifecycle of a MSFR II number density (atoms/barn cm) 1.0 *10-3 transmuter operation deep burn phase U-233 Pu-239 Pu Pu-241 Pu-242 Am Am-243 Cm-244 Cm Burnup [GWd/tHM] nuclide inventory evolution in the 2D calculation transmuter operation: re-feeding of TRU during build up of U-233 fuel from Th fertile deep burn phase: re-feeding of U-233 bred in the blanket during operation Seite 26/30

27 Development of Inventories in deep burn phase number density (atoms/barn cm) 0.9 *10-3 transmuter operation Pu-239 Pu-240 Pu-241 Pu Burnup [GWd/tHM] deep burn phase number density (atoms/barn cm) 0.6 Am-241 Am-243 Cm-244 Cm *10-4 transmuter operation Burnup [GWd/tHM] deep burn phase *10-7 transmuter operation deep burn phase number density (atoms/barn cm) Cf-249 Cf Burnup [GWd/tHM] Plutionium, Americium, and Curium can be burnt Only Californium is accumulated in very limited amount (~1.5 kg) Seite 27/30

28 Conclusions and Outlook Text optional: Institutsname Prof. Dr. Hans Mustermann Mitglied der Leibniz-Gemeinschaft

29 Extension of the DYN3D code Validation of a diverse coupled 3d core simulation system in good progress Liquid metal technology Advanced instrumentation, visualization techniques and components pouring concrete phase Kinetic solutions without space-time separation for experimental analysis New, improved onset for analysis of ADS experiments is in good progress, some findings are confirmed by experiments Use of Moderating Material to Improve the Safety Characteristics in SFR Creation of a new degree of freedom for SFR design and transmutation optimization is extended to HLM fast reactor Molten Salt Reactor for the Nuclear Phase Out Twofold Lifecycle transmuter and deep burn phase Seite 29/30

30 Welcome to PLOS ONE! I have joined the Academic Editorial Board of PLOS ONE for the broad area of nuclear Manuscripts are highly welcome Seite 30/30