Published 1988
| Version v1
Book
Analyzing unprotected transients in metal fuel cores with the SAS4A accident analysis code
- 1. Argonne National Lab., IL (USA). Reactor Analysis and Safety Div.
Description
The SAS4A code has been designed to simulate events that occur in a liquid metal reactor (LMR) core during the initiating phase of a severe unprotected accident. To adapt the SAS4A code to analysis of metal fuel cores, new models have been developed. This paper describes current SAS4A capabilities and emphasizes the influence of metal fuel characteristics on whole core behaviour during the accident
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 89448-1460-0
- Imprint Title
- Proceedings of the international topical meeting on safety of next generation power reactors
- Imprint Pagination
- 933 p.
- Journal Page Range
- p. 799-805.
Conference
- Title
- American Nuclear Society topical meeting on the safety of next generation power reactors.
- Dates
- 1-5 May 1988.
- Place
- Seattle, WA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22023565
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; LIQUID METAL COOLED REACTORS; REACTOR CORES; REACTOR OPERATION; REACTOR SAFETY; S CODES; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; OPERATION; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION
Optional Information
- Secondary number(s)
- CONF-880506--.