Published 1992
| Version v1
Book
Computer aided analysis of the transient behaviour of nuclear reactor containment
- 1. Bhabha Atomic Research Centre, Bombay (India). Reactor Safety Division
Description
The computer codes describing various physical processes, encountered during postulated accident conditions, such as fluid dynamics, heat transfer, structural dynamics etc. have become the basic tools for the analysis of the behaviour of nuclear reactor containments. The computer code also helps in understanding and interpreting the experimental observations. This paper deals with the use of computer for containment safety analysis. Salient features of a multicompartment thermal hydraulic transient analysis code CONTRAN are also presented. (author). 11 refs., 4 figs
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre.
- Imprint Place
- Bombay (India)
- Imprint Title
- Proceedings of national symposium on computer applications in power plants
- Imprint Pagination
- 557 p.
- Journal Page Range
- p. 303-308.
Conference
- Title
- National symposium on computer applications in power plants.
- Dates
- 8-10 Dec 1992.
- Place
- Bombay (India).
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 26024590
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BLOWDOWN; C CODES; COMPUTERIZED SIMULATION; CONTAINMENT; HEAT SINKS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MATHEMATICAL MODELS; MICROCOMPUTERS; PHWR TYPE REACTORS; SAFETY ANALYSIS; STEAM; THERMODYNAMICS; TIME DEPENDENCE; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COMPUTERS; DIGITAL COMPUTERS; ENERGY TRANSFER; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION