Published April 1994
| Version v1
Journal article
Stability, accuracy, and convergence of the numerical methods in RELAP3/MOD3
- 1. EG ampersand G Idaho, Inc., Idaho Falls, ID (United States). Idaho National Engineering Lab.
- 2. Pacific Nuclear, Westmont, IL (United States)
- 3. Purdue Univ., West Lafayette, IN (United States). Dept. of Nuclear Engineering
Description
Both theoretical and numerical results on the relationships between the magnitude of the interphase drag coefficients, the mesh size, and the stability of the semi-implicit method used in RELAP5 are presented. It is shown that the numerical solutions are both stable and convergent on meshes with a characteristic ratio (ratio of mesh size-to-hydraulic diameter) that is not too small, that the code is capable of simulating physical instabilities on coarse meshes, and that unphysical instabilities will occur only at small mesh size even for problems that admit physical instabilities. Good transition from pre-critical heat flux (CHF) to post-CHF, however, is necessary to improve the accuracy of certain calculations
Additional details
Publishing Information
- Journal Title
- Nuclear Science and Engineering
- Journal Volume
- 116
- Journal Issue
- 4
- Journal Page Range
- p. 227-244.
- ISSN
- 0029-5639
- CODEN
- NSENAO
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25067139
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRITICAL HEAT FLUX; MESH GENERATION; NUMERICAL SOLUTION; PARTIAL DIFFERENTIAL EQUATIONS; R CODES; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; TRANSIENTS; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; DIFFERENTIAL EQUATIONS; EQUATIONS; HEAT FLUX; REACTOR COMPONENTS; REACTORS; SIMULATION