Published February 15, 2006
| Version v1
Miscellaneous
Gas Cooled Reactors Neutronic Simulation: VSOP vs. MCNP Benchmark
- 1. Department of Nuclear Engineering, Ben Gurion University, Beer-Sheva (Israel)
Description
The fast and thermal spectrum gas-cooled reactors are both chosen by the international board of experts as two out of the six most promising Generation IV nuclear reactor concepts. As a result, an extensive research and development effort is ongoing worldwide to design the next generation of gas-cooled reactors . The objective of this analysis is to test the calculation tool - the VSOP(1) computer code system available for gas-cooled reactors neutronic simulation against state of the art Monte Carlo particles transport code MCNP-4C. A series of benchmark calculations was performed in a unit cell and full core configurations typical of pebble bed gas-cooled reactor
Additional details
Publishing Information
- Imprint Title
- The 23. conference of the Nuclear Societies in Israel. Book of articles
- Imprint Pagination
- 256 p.
- Journal Page Range
- p. 24-26
- Report number
- INIS-IL--012
Conference
- Title
- 23. conference of the Nuclear Societies in Israel
- Dates
- 15-16 Feb 2006
- Place
- Dead Sea (Israel)
INIS
- Country of Publication
- Israel
- Country of Input or Organization
- Israel
- INIS RN
- 38093014
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COMPARATIVE EVALUATIONS; COMPUTER CODES; COMPUTERIZED SIMULATION; CRITICALITY; GCFR REACTOR; GCR TYPE REACTORS; MONTE CARLO METHOD; REACTOR KINETICS; REACTOR LATTICE PARAMETERS; REACTOR PHYSICS; THERMAL REACTORS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BREEDER REACTORS; CALCULATION METHODS; EPITHERMAL REACTORS; EVALUATION; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; GCFR TYPE REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; KINETICS; PHYSICS; REACTORS; SIMULATION