Fast Reactor Research in Dresden-Rossendorf

Transcription

1 Fast Reactor Research in Dresden-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 Seite 2/18

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 4/18

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 working at the nelbe photoneutron source Seite 5/18

6 Contactless Inductive Flow Tomography (CIFT) A fully contactless technique to measure the 3D mean flow field in electrically conducting melt (analog Magnetoencephalographie in medicine) Developed over past decade at HZDR: Theory developed in Demo-experiment in Status: transfer to real problems in progress (steel casting, silicon crystal growth) T. Wondrak et al., Meas. Sci. Techn. 21, , T. Wondrak et al., Met. Mat. Transactions 42B, 1201, F. Stefani, G. Gerbeth, Inverse Problems 15, 771, F. Stefani, G. Gerbeth, Meas. Sci. Techn. 11, 758, F. Stefani, T. Gundrum, G. Gerbeth, Phys. Rev. E. 70, , A flow field modifies an external magnetic field: B = B 0 + b, b ~ R m B 0 (R m = µσlv) the magnetic field measured outside the melt contains information about the flow field Gives in a robust way the 3D mean flow field every ~ 1s Application in industrial silicon crystal growth: Seite 6/18

7 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 7/18

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

9 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 9/18

10 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 10/18

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

12 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 12/18 ready to be validated for steady state coupling with TRANSURANUS VHTR benchmark

13 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 13/18

14 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 14/18

15 IAEA CRP on EBR-II Benchmark There will be two major contributions from Germany from the SIMMER group a coordinated German contribution (HZDR GRS KIT-INR) using updated LWR tools for coupled calculations ATHLET System code DYN3D Core simulator SERPENT XS preparation SUBCHANFLOW Subchannel analysis code Seite 15/18

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

17 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 17/18

18 Enhanced Feedback Coefficients change reactivity coeff. [%] reference Doppler coefficient Coolant coefficient wire spacer Significant improvement of Doppler coefficient Reduction of positive coolant coefficient 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 Seite 18/18

19 Influence on Americium Transmutation Rates Transmutation rates for assemblies with and without moderating material up to ~ 50% Am-241 and up to 30% Am-243 is transmuted transmutation rate increases significantly with increasing Americium share in the fuel Influence on feedback coefficients and fuel performance limits the Americium share Use of moderating material can compensate the effect of Americium on feedback coefficients A slight increase in Curium production (~5%) has to be accepted Seite 19/18

20 Conclusions Extension of the DYN3D code Validation of a diverse coupled 3d core simulation system Liquid metal technology Advanced instrumentation, visualization techniques and components, new big scale experimental facility Kinetic solutions without space-time separation for experimental analysis New, improved onset for analysis of ADS 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 Seite 20/18