Published August 1984
| Version v1
Report
Limit load analysis of actual spherical containments subjected to static internal pressure and temperature
Description
The report describes potential sources of leakage for a PWR 1300 spherical metal containment. The critical internal pressure and temperature are given depending on certain influence parameters. Mainly because of the high-ductile material used leakage-before-failure seems to be likely
Additional details
Publishing Information
- Imprint Title
- Proceedings of the second workshop on containment integrity
- Journal Page Range
- p. 287-304.
- Report number
- NUREG/CP--0056
Conference
- Title
- 2. workshop on containment integrity.
- Dates
- 13-15 Jun 1984.
- Place
- Crystal City, VA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16064806
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SHELLS; CRACKS; CREEP; DEFORMATION; DUCTILITY; FAILURES; FRACTURE MECHANICS; LEAKS; PRESSURE DEPENDENCE; PRESSURE VESSELS; PRESSURIZATION; PWR TYPE REACTORS; RELIABILITY; SPHERICAL CONFIGURATION; STATIC LOADS; STRESS ANALYSIS; STRESSES
- Descriptors DEC
- CONFIGURATION; CONTAINERS; CONTAINMENT; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; MECHANICS; POWER REACTORS; REACTORS; TENSILE PROPERTIES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS