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AbstractAbstract
[en] The present work is the results of JNC, Japan, for the Phase 4 of the BN-600 core benchmark problem (Hex-Z fully MOX fuelled core model) organized by IAEA. The benchmark specification is based on 1) the RCM report of IAEA CRP on 'Updated Codes and Methods to Reduce the Calculational Uncertainties of LMFR Reactivity Effects, Action 3.12' (Calculations for BN-600 fully fuelled MOX core for subsequent transient analyses). JENDL-3.2 nuclear data library was used for calculating 70 group ABBN-type group constants. Cell models for fuel assembly and control rod calculations were applied: homogeneous and heterogeneous (cylindrical supercell) model. Basic diffusion calculation was three-dimensional Hex-Z model, 18 group (Citation code). Transport calculations were 18 group, three-dimensional (NSHEC code) based on Sn-transport nodal method developed at JNC. The generated thermal power per fission was based on Sher's data corrected on the basis of ENDF/B-IV data library. Calculation results are presented in Tables for intercomparison
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Source
International Atomic Energy Agency, Technical Working Group on Fast Reactors, Vienna (Austria); 444 p; 2003; p. 179-193; 4. research co-ordination meeting (RCM) on 'Updated codes and methods to reduce the calculational uncertainties of liquid metal fast reactors reactivity effects'; Obninsk (Russian Federation); 19-23 May 2003; Tabs
Record Type
Report
Literature Type
Conference
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BELOYARSK-3 REACTOR, BENCHMARKS, COMPARATIVE EVALUATIONS, CONTROL ELEMENTS, CYLINDRICAL CONFIGURATION, DISCRETE ORDINATE METHOD, FUEL ASSEMBLIES, GROUP CONSTANTS, MIXED OXIDE FUELS, NEUTRON DIFFUSION EQUATION, NEUTRON TRANSPORT THEORY, NUCLEAR DATA COLLECTIONS, THERMAL FISSION, THREE-DIMENSIONAL CALCULATIONS
BARYON REACTIONS, BREEDER REACTORS, CALCULATION METHODS, CONFIGURATION, CROSS SECTIONS, DIFFERENTIAL EQUATIONS, DIFFUSION EQUATIONS, ENERGY SOURCES, EPITHERMAL REACTORS, EQUATIONS, EVALUATION, FAST REACTORS, FBR TYPE REACTORS, FISSION, FUELS, HADRON REACTIONS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MATERIALS, NEUTRON REACTIONS, NUCLEAR FUELS, NUCLEAR REACTIONS, NUCLEON REACTIONS, PARTIAL DIFFERENTIAL EQUATIONS, POWER REACTORS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, SODIUM COOLED REACTORS, SOLID FUELS, TRANSPORT THEORY
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