MTR core loading pattern optimization using burnup dependent group constant
Creators
- 1. Nuclear Engineering Division, Pakistan Institute of Nuclear Science and Engineering (PINSTECH), Nilore, Islamabad 45650, (Pakistan)
- 2. Department of Physics and Applied Mathematics, Pakistan Institute of Engineering and Applied Sciences (PIEAS), Nilore, Islamabad 45650, (Pakistan)
Description
A diffusion theory based MTR fuel management methodology has been developed for finding superior core loading patterns at any stage for MTR systems, keeping track of burnup of individual fuel assemblies throughout their history. It is based on using burnup dependent group constants obtained by the WIMS-D/4 computer code for standard fuel elements and control fuel elements. This methodology has been implemented in a computer program named BFMTR, which carries out detailed five group diffusion theory calculations using the CITATION code as a subroutine. The core-wide spatial flux and power profiles thus obtained are used for calculating the peak-to-average power- and flux-ratios along with the available excess reactivity of the system. The fuel manager can use the BFMTR code for loading pattern optimization for maximizing the excess reactivity, keeping the peak-to-average power as well as flux-ratio within constraints. The results obtained by the BFMTR code have been found to be in good agreement with the corresponding experimental values for the equilibrium core of the Pakistan Research Reactor-1. (author)
Availability note (English)
Also available online from http://ntrp.vinca.rs/ArchiveF.htmAdditional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Technology and Radiation Protection
- Journal Volume
- 23
- Journal Issue
- 2
- Journal Page Range
- p. 28-33
- ISSN
- 1451-3994
INIS
- Country of Publication
- Serbia
- Country of Input or Organization
- Serbia
- INIS RN
- 40106059
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BURNUP; COMPUTER CODES; CONTROL ELEMENTS; EVALUATED DATA; EXPERIMENTAL DATA; FUEL ASSEMBLIES; FUEL ELEMENTS; FUEL MANAGEMENT; GROUP CONSTANTS; MTR REACTOR; NUCLEAR CORES; OPTIMIZATION; PARR-1 REACTOR; REACTOR CORES; REACTOR FUELING; THERMAL COLUMNS; THERMAL NEUTRONS
- Descriptors DEC
- BARYONS; CROSS SECTIONS; DATA; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; INFORMATION; IRRADIATION REACTORS; MANAGEMENT; MATERIALS TESTING REACTORS; NEUTRONS; NUCLEAR MATERIALS MANAGEMENT; NUCLEONS; NUMERICAL DATA; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 12 refs., 5 figs., 1 tab.