Nuclear analysis method based on current coupling neutron response reconstruction method
- 1. Hitachi, Ltd., Research & Development Group, Hitachi, Ibaraki (Japan)
Description
The current coupling neutron response reconstruction method has been developed, based on the already developed direct response matrix method. In the current coupling neutron response reconstruction method, by setting fuel rod neutron production rates as new unknown values, the need to calculate the response matrix is eliminated, and the calculation time can be reduced compared to the direct response matrix method. Furthermore, by evaluating the neutron fluxes and the cross sections using the reconstruction method of homogenized cross sections which has already been developed, the neutron effective multiplication factor is directly evaluated from the reaction rate ratio, and convergence can be improved. For the purpose of verification, calculations for heterogeneous systems were performed. The results obtained using the current coupling neutron response reconstruction method agreed well with those obtained using direct calculations by the Monte Carlo method, and they were almost the same as those obtained using the direct response matrix method. These good agreements with the direct calculations using the Monte Carlo method meant that the current coupling neutron response reconstruction method accurately reflected the effects of intra- and inter-assembly heterogeneities. In terms of calculation time, the current coupling neutron response reconstruction method was 33 to 60 times faster than the direct response matrix method by eliminating the need for a response matrix and improving convergence. (author)
Availability note (English)
Available from DOI: https://doi.org/10.1080/00223131.2022.2142309Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo) (Online)
- Journal Volume
- 60
- Journal Issue
- 7
- Journal Page Range
- p. 759-768
- ISSN
- 1881-1248
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 56002693
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BWR TYPE REACTORS; CROSS SECTIONS; FUEL ASSEMBLIES; FUEL RODS; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NEUTRON FLUX; NEUTRON TRANSPORT; NUCLEAR REACTIONS; REACTOR CORES; RESPONSE MATRIX METHOD; V CODES
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; DIMENSIONLESS NUMBERS; ENRICHED URANIUM REACTORS; EQUATIONS; FUEL ELEMENTS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; RADIATION FLUX; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTOR KINETICS EQUATIONS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 10 refs., 8 figs., 4 tabs.