A nodal method with technique of thermal neutron decoupling
Description
An advanced nodal method with decoupling model for the solution of the multidimensional neutron diffusion equation is developed. The relationship between fast flux and thermal flux is established with the help of the analytical solution of the two group neutron diffusion equation. Using this relationship the two group equation is decoupled, reducing the problem of solving the two group equation to that of solving the fast group equation only. The fast group equation is solved by the Green's function method. A computer code NGMD has been encoded based on the proposed method and has been tested by several LWR benchmark problems. The numerical results demonstrate that NGMD has almost the same accuracy as the well-known nodal code NGFM while its CPU time is only about 1/3 of that of NGFM
Additional details
Publishing Information
- Journal Title
- Chinese Journal of Nuclear Science and Engineering
- Journal Volume
- 18
- Journal Issue
- 1
- Journal Page Range
- p. 42-52.
- ISSN
- 0258-0918
- CODEN
- HYGODG
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 29029378
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- ANALYTICAL SOLUTION; BWR TYPE REACTORS; ERRORS; FUEL MANAGEMENT; MATHEMATICAL MODELS; N CODES; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NODAL EXPANSION METHOD; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTOR CORES; THERMAL NEUTRONS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; COMPUTER CODES; DISTRIBUTION; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; MANAGEMENT; NEUTRONS; NUCLEAR MATERIALS MANAGEMENT; NUCLEONS; POWER REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS