Development of a multiple perturbation Monte Carlo methods for criticality problems and implementation on parallel processors
Creators
- 1. Michigan Univ., Ann Arbor, MI (United States). Dept. of Nuclear Engineering
Description
Monte Carlo correlated sampling technique has been combined with the fission matrix method to calculate reactivity perturbations due to small changes in cross-sections. The actual Monte Carlo simulation is performed a reference system different from both the unperturbed and perturbed systems. This approach allows to correlated the unperturbed system and multiple perturbed systems to the reference system. Hence it is possible to determine multiple reactivities due to multiple cross-section perturbations from a single Monte Carlo simulation. This method has been tested for once energy group isotropic scattering problems. It was also implemented the fission matrix algorithm for eigenvalue calculation and the multiple reactivity calculation algorithm on the IBM-SP2 parallel processor. Speedup performances from IBM-SP2 parallel computer are presented and a theoretical model is used to predict the speedup curves. (author) 8 refs, 2 figs
Additional details
Additional titles
- Original title (English)
- Anais do 10. Encontro de Fisica de Reatores e Termo-Hidraulica.
Publishing Information
- Imprint Title
- Proceedings of the 10. Meeting on Reactor Physics and Thermal Hydraulics
- Imprint Pagination
- 563 p.
- Journal Page Range
- p. 1-6.
Conference
- Title
- 10. Meeting on Reactor Physics and Thermal Hydraulics.
- Original Conference Title
- 10. Encontro de Fisica de Reatores e Termo-Hidraulica
- Dates
- 7-11 Aug 1995.
- Place
- Aguas de Lindoia, SP (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 27014950
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CRITICALITY; FISSION; FUEL ASSEMBLIES; FUEL ELEMENTS; MONTE CARLO METHOD; NEUTRON TRANSPORT THEORY; PARALLEL PROCESSING; REACTOR CORES; REACTOR KINETICS; REACTOR PHYSICS; REACTORS; RESEARCH REACTORS
- Descriptors DEC
- CALCULATION METHODS; KINETICS; NUCLEAR REACTIONS; PROGRAMMING; REACTOR COMPONENTS; RESEARCH AND TEST REACTORS; TRANSPORT THEORY
Optional Information
- Notes
- Imprint:Joint nuclear conference with the 3. Brazilian Meeting on Nuclear Applications.;Anais do 10. Encontro de Fisica de Reatores e Termo-Hidraulica.