Published October 1984
| Version v1
Journal article
Numerical calculations for two-phase flow analyses in pin bundles
Creators
- 1. Toshiba Corp., Kawasaki, Kanagawa (Japan). Research and Development Center
- 2. Toshiba Corp., Kanagawa (Japan). Nuclear Engineering Lab.
Description
Two-phase flow equation systems, in which equations are defined for each phase, are discussed for use in analyzing coolant behaviors in LMFBR pin bundles. These equation systems have not yet consolidated, because of theoretical and experimental difficulties and complexities. One of the problems is the equation systems' stability. This paper shows the stability for the low Reynolds number (O(1)) system, using a one dimensional linear equation system. Based on this fact, a two-phase flow equation system is numerically solved by using the subchannel method for 19- and 37-pin bundles. The calculational examples are LOF and TOP conditions with/without the blockage, and fission gas release. (orig.)
Additional details
Publishing Information
- Journal Title
- Nucl. Eng. Des.
- Journal Volume
- 82
- Journal Issue
- 2/3
- Series
- CODEN: NEDEA.;Nucl. Eng. Des.
- Journal Page Range
- 157-169
- ISSN
- 0029-5493
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 16027430
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FISSION PRODUCT RELEASE; FLOW BLOCKAGE; FLOWSHEETS; FUEL ELEMENT CLUSTERS; LMFBR TYPE REACTORS; LOSS OF FLOW; MESH GENERATION; NEWTON METHOD; NUMERICAL SOLUTION; SIMULATION; STABILITY; TWO-PHASE FLOW; VELOCITY
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; DIAGRAMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; FUEL ASSEMBLIES; INFORMATION; ITERATIVE METHODS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS