Published 1987
| Version v1
Journal article
Heat transfer R and D in support of CANDU reactors
Creators
- 1. Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.
Description
The paper reviews various types of thermalhydraulic models used in computational analysis in support of reactor design, and concentrates on particular areas of research and development, fundamental to defining accurately the various modes of heat transfer upon which reactor operation depends. (28 refs., 9 figs., tab.)
Additional details
Publishing Information
- Journal Title
- Transactions of the Canadian Society for Mechanical Engineering
- Journal Volume
- 11
- Journal Issue
- 3
- Journal Page Range
- p. 1-9.
- ISSN
- 0315-8977
- CODEN
- TCMEAP
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 24007459
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- C CODES; CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; CRITICAL HEAT FLUX; F CODES; FLOW MODELS; HEAT TRANSFER; NUMERICAL ANALYSIS; PRIMARY COOLANT CIRCUITS; RESEARCH PROGRAMS; S CODES; TWO-PHASE FLOW
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; FLUID FLOW; HEAT FLUX; HEAVY WATER MODERATED REACTORS; MATHEMATICAL MODELS; MATHEMATICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS