Published 1995 | Version v1
Miscellaneous

Development of a multiple perturbation Monte Carlo methods for criticality problems and implementation on parallel processors

  • 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

Part of:
Proceedings of the 10. Meeting on Reactor Physics and Thermal Hydraulics

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.