Leakage potential through mechanical penetrations in a severe accident environment
Description
This paper reviews the findings of an ongoing program, ''Integrity of Containment Penetrations Under Severe Accident Loads.'' The program is concerned with the leakage modes as well as the magnitude of leakage through mechanical penetrations in a containment building subject to a severe accident. Seal and gasket tests are used to evaluate the effect of radiation aging, thermal aging, seal geometry, and seal squeeze on seals and gaskets subjected to a hypothesized severe accident. The effects on leakage of the structural response of equipment hatches, personnel airlocks, and drywell heads subjected to severe accident pressures are studied by experiments and analyses. The data gathered during this program will be used to develop methodologies for predicting leakage
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as TI86011654.
Files
Additional details
Publishing Information
- Imprint Pagination
- 14 p.
- Report number
- SAND--86-2077C
Conference
- Title
- 3. workshop on integrity of containments for nuclear power plants.
- Dates
- 21-23 May 1986.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17089409
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; BUILDINGS; BWR TYPE REACTORS; CONTAINMENT SYSTEMS; LEAKS; PHYSICAL RADIATION EFFECTS; PWR TYPE REACTORS; REACTOR MATERIALS
- Descriptors DEC
- CONTAINMENT; ENRICHED URANIUM REACTORS; MATERIALS; POWER REACTORS; RADIATION EFFECTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-860507--10.