Calculation of HTR-10 first criticality with MVP
Description
The first criticality of 10 MW pebble-bed high temperature gas-cooled reactor-test module (HTR-10) was calculated with MVP. According to the characteristics of HTR-10, the Statistical Geometry Model of MVP was employed to describe the random arrangement of coated fuel particles in the fuel pebbles and the random distribution of the fuel and dummy pebbles in the core. Compared with previous results from VSOP and MCNP, the MVP results with JENDL-3.3 library were little more different, but the results with ENDF/B-Ⅵ.8 library were very close. The relative errors were less than 0.7%, compared with the first criticality experimental results. The study shows that MVP could be used in the physics calculations for pebble bed high temperature gas-cooled reactors. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 36
- Journal Issue
- 2
- Journal Page Range
- p. 9-12
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 48083757
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Descriptors DEI
- COATED FUEL PARTICLES; COMPARATIVE EVALUATIONS; CRITICALITY; DISTRIBUTION; ERRORS; FUEL ELEMENTS; GEOMETRY; GRAPHITE; HTR-10 REACTOR; M CODES; NUCLEAR DATA COLLECTIONS; RANDOMNESS; SPHERES
- Descriptors DEC
- CARBON; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM REACTORS; EVALUATION; EXPERIMENTAL REACTORS; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MATHEMATICS; MINERALS; NONMETALS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TEST FACILITIES; TEST REACTORS
Optional Information
- Notes
- 6 tabs., 6 refs.