Development of spectral history methods for pin-by-pin core analysis method using three-dimensional direct response matrix
Creators
- 1. Energy and Environmental Systems Laboratory, Hitachi, Ltd., 2-1 Omika-cho, 7-chome, Hitachi-shi Ibaraki-ken, 319-1221 (Japan)
Description
Spectral history methods for pin-by-pin core analysis method using the three-dimensional direct response matrix have been developed. The direct response matrix is formalized by four sub-response matrices in order to respond to a core eigenvalue k and thus can be recomposed at each outer iteration in the core analysis. For core analysis, it is necessary to take into account the burn-up effect related to spectral history. One of the methods is to evaluate the nodal burn-up spectrum obtained using the out-going neutron current. The other is to correct the fuel rod neutron production rates obtained the pin-by-pin correction. These spectral history methods were tested in a heterogeneous system. The test results show that the neutron multiplication factor error can be reduced by half during burn-up, the nodal neutron production rates errors can be reduced by 30% or more. The root-mean-square differences between the relative fuel rod neutron production rate distributions can be reduced within 1.1% error. This means that these methods can accurately reflect the effects of intra- and inter-assembly heterogeneities during burn-up and can be used for core analysis. Core analysis with the DRM method was carried out for an ABWR quarter core and it was found that both thermal power and coolant-flow distributions were smoothly converged. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-069-0
- Imprint Pagination
- 12 p.
Conference
- Title
- 2009 International Conference on Advances in Mathematics, Computational Methods, and Reactor Physics
- Acronym
- M and C 2009
- Dates
- 3-7 May 2009
- Place
- Saratoga Springs, NY (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 42061006
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; EIGENFUNCTIONS; EIGENVALUES; ERRORS; FUEL RODS; MATRICES; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NEUTRONS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; DIMENSIONLESS NUMBERS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; FUEL ELEMENTS; FUNCTIONS; HADRONS; NUCLEONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 refs.