Published 1991
| Version v1
Journal article
New insights into managing severe accidents
Creators
Description
A large body of severe accident information is available today. The nuclear community is invited to use the information at hand to generate two figures. The first would display consequences compared with ΔT, where ΔT is the difference in time between the onset of core damage and the release of significant amounts of radioactive material into the environment. It is expected that consequences would maximize when ΔT is small. The second would plot cumulative core-melt frequency against primary system break area. It is expected that the preponderance of the core-melt frequency would be found in the zero to small break area range. The author's concept on how these figures might look is provided here
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Journal Page Range
- p. 366-367.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics.
- Dates
- 10-15 Nov 1991.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24015888
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOUNDARY CONDITIONS; BWR TYPE REACTORS; CHERNOBYLSK-4 REACTOR; CONTAINMENT SYSTEMS; ECCS; ENGINEERED SAFETY SYSTEMS; FAILURES; FUEL ELEMENT FAILURE; MELTDOWN; MITIGATION; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PROBABILITY; PUMPS; PWR TYPE REACTORS; RADIOACTIVE AEROSOLS; RADIOACTIVITY TRANSPORT; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR VESSELS; THREE MILE ISLAND-2 REACTOR; US NRC
- Descriptors DEC
- ACCIDENTS; AEROSOLS; COLLOIDS; CONTAINERS; CONTAINMENT; COOLING SYSTEMS; DISPERSIONS; ENRICHED URANIUM REACTORS; EQUIPMENT; GRAPHITE MODERATED REACTORS; LWGR TYPE REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SOLS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911107--.