Published 1995
| Version v1
Journal article
Reactor coolant system depressurization in PWRs with U-tube steam generators
Creators
- 1. Idaho National Engineering Lab., Idaho Falls, ID (United States)
Description
Molten core materials could be ejected into the containment building by a high-pressure reactor coolant system (RCS) following reactor vessel failure during certain severe accidents. A rapid rise in containment temperature and pressure, or direct containment heating (DCH), could result from that high-pressure melt ejection (HPME). In an extreme case, the pressurization associated with DCH could lead to containment failure
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 73
- Journal Page Range
- p. 493-494.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS).
- Dates
- 29 Oct - 1 Nov 1995.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28018987
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SYSTEMS; DEPRESSURIZATION; FAILURES; HEATING; HYDRAULICS; PWR TYPE REACTORS; R CODES; REACTOR ACCIDENTS; S CODES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINMENT; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-951006--.