Few group diffusion calculations of a light water moderated lattice
Creators
- 1. Nippon Atomic Industry Group Co., Ltd., NAIG Nuclear Research Laboratory, Kawasaki, Kanagawa (Japan)
- 2. Tokyo Shibaura Electric Co., Ltd., Central Research Laboratory, Kawasaki, Kanagawa (Japan)
Description
An analysis was made of a light water moderated lattice based on few group diffusion calculations. The lattice under investigation consisted of 468 fuel rods in a square lattice arranged in a cylindrical core of 22.46 cm effective radius and 127.2 cm core height, with a water to fuel volume ratio of 2.918. The fuel was 2.02% enriched UO2, clad in 0.8 mm thick aluminum tube. The theoretically calculated values for thermal, epithermal and fast neutron flux distributions, as well as the effective multiplication constant λ of the lattice, were compared with experimental data. After detailed analysis of the problems encountered in the course of the study the value of 0.9935 was determined for λ. Uncertainty in the nuclear data for fast neutrons would appear to constitute the greatest factor of error in λ. The discrepancies between the calculated and experimental activation distributions of the thermal, epithermal and fast neutrons amounted for about 20, 10 and 15%, respectively, in the reflector region adjoining the core. The fact that these discrepancies cannot be removed by multigroup P1 calculations would point toward insufficiency of the diffusion or P1 calculation this region. It was also concluded that the following items could not be neglected without causing an error in λ of more than 0.3% in the particular lattice under investigation: (1) Heterogeneity in the fast neutron energy region. (2) Intra-cell change of thermal neutron spectrum. (3) Macroscopic spectral change near the core-reflector interface. (author)
Availability note (English)
Available from DOI: https://doi.org/10.1080/18811248.1966.9732335Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo) (Online)
- Journal Volume
- 3
- Journal Issue
- 8
- Journal Page Range
- p. 309-319
- ISSN
- 1881-1248
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 54021790
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Descriptors DEI
- CROSS SECTIONS; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NEUTRON REFLECTORS; NUCLEAR DATA COLLECTIONS; NUCLEAR FUELS; RADIOACTIVATION; REACTOR LATTICES; WATER COOLED REACTORS; WIGNER-WILKINS MODEL
- Descriptors DEC
- DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ENERGY SOURCES; EQUATIONS; FUELS; MATERIALS; NEUTRON TRANSPORT THEORY; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION FLUX; REACTOR MATERIALS; REACTORS; TRANSPORT THEORY
Optional Information
- Notes
- 19 refs., 13 figs., 3 tabs.