Published November 2010
| Version v1
Journal article
Development of calculation technique for iterated fission probability and reactor kinetic parameters using continuous-energy Monte Carlo method
Creators
- 1. Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan)
Description
New algorithms and techniques are developed for calculating the iterated fission probability (IFP) using a Monte Carlo eigenvalue calculation scheme. The proportionality of the calculated IFP to the adjoint flux is confirmed numerically. This IFP is then used with the MCNP code and its point-wise cross section data libraries to calculate kinetic parameters weighted by the adjoint flux. Experimental data for critical cores validate these theoretical estimates. (author)
Availability note (English)
Available from http://dx.doi.org/10.3327/jnst.47.977Additional details
Identifiers
- DOI
- 10.3327/jnst.47.977;
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 47
- Journal Issue
- 11
- Journal Page Range
- p. 977-990
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 42014475
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ADJOINT FLUX; ALGORITHMS; CHAIN REACTIONS; COMPARATIVE EVALUATIONS; DELAYED NEUTRON FRACTION; EIGENVALUES; FISSION; M CODES; MONTE CARLO METHOD; PROBABILITY; REACTOR KINETICS; WEIGHTING FUNCTIONS
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; EVALUATION; FUNCTIONS; KINETICS; MATHEMATICAL LOGIC; NEUTRON FLUX; NUCLEAR REACTIONS; RADIATION FLUX
Optional Information
- Notes
- 32 refs., 10 figs., 5 tabs.