Advanced modelling methods in Monte Carlo
Description
In the WIMS7 reactor physics program scheme a three dimensional microscopic depletion method has recently been developed, using Monte Carlo fluxes. Extensions of the method enabling users to evaluate reactivity coefficients and point powers have also been added. These methods, which include whole core calculations, have been implemented in the long established companion code MONK5W. Predictions at successive depletion time steps are thus based on a calculational route where both geometry and cross sections are accurately represented, providing a reliable and independent reactor physics analysis package for benchmarking other methods. Newly developed tracking and storage procedures in MONK5W enable whole core burnup modelling on a desktop computer. Theory and applications are presented. (author)
Additional details
Publishing Information
- Imprint Title
- International conference on the physics of reactors PHYSOR96, vol. 1
- Imprint Pagination
- 615 p.
- Journal Page Range
- p. A/202-A/211.
Conference
- Title
- international conference on the physics of reactors 1996.
- Acronym
- PHYSOR96
- Dates
- 16-20 Sep 1996.
- Place
- Mito (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 28021768
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ADJOINT FLUX; BURNUP; M CODES; MONTE CARLO METHOD; NEUTRON TRANSPORT THEORY; PERTURBATION THEORY; PWR TYPE REACTORS; REACTIVITY COEFFICIENTS; REACTIVITY WORTHS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; ENRICHED URANIUM REACTORS; NEUTRON FLUX; POWER REACTORS; RADIATION FLUX; REACTORS; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Published in 4 volumes.