Published October 2002
| Version v1
Journal article
Nonlinear analytic and semi-analytic nodal methods for multigroup neutron diffusion calculations
Creators
- 1. Korea Advanced Inst. of Science and Technology, Dept. of Nuclear and Quantum Engineering, Taejon (Korea, Republic of)
Description
Two advanced nodal methods for the solution of the multigroup neutron diffusion equations are developed, using the nonlinear coarse-mesh finite difference (CMFD) scheme. Based on the analytic and semi-analytic method, the relationships between the flux and current on the nodal surface are derived, by which the two-node problem is formulated in an efficient way. The issue of the complex eigenmodes and the instability problem inherent in the analytic solution are considered in order to have an efficient and stable algorithm. The numerical results demonstrate the effectiveness of the two methods. (author)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 39
- Journal Issue
- 10
- Journal Page Range
- p. 1015-1025
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 33069814
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ALGORITHMS; ANALYTIC FUNCTIONS; ANALYTICAL SOLUTION; FINITE DIFFERENCE METHOD; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION; NODAL EXPANSION METHOD; NONLINEAR PROBLEMS
- Descriptors DEC
- CALCULATION METHODS; DIFFERENTIAL EQUATIONS; EQUATIONS; FUNCTIONS; ITERATIVE METHODS; MATHEMATICAL LOGIC; NEUTRON TRANSPORT THEORY; NUMERICAL SOLUTION; TRANSPORT THEORY
Optional Information
- Notes
- 20 refs., 3 figs., 7 tabs.