Published 1989
| Version v1
Book
Extreme pressure and thermal loads on 500 MWe PHWR containment following steam line break
Description
Vapor suppression type of containment calls for containment to be divided into two accident based volumes, drywell and wetwell, separated by leaktight walls and floors. Reactor building containment structure is designed to withstand extreme load conditions following postulated accidents. In this paper methodology adopted for calculation of R.B. peak pressure and temperature is discussed and results of pressure and temperature transients following a steam line break within the containment are reported
Additional details
Publishing Information
- Publisher
- American Association for Structural Mechanics in Reactor Technology.
- Imprint Place
- Los Angeles, CA (USA)
- ISBN
- 0-9623306-0-4
- Imprint Title
- Transactions of the 10th international conference on structural mechanics in reactor technology
- Imprint Pagination
- 337 p.
- Series
- Extreme loads analysis.
- Journal Page Range
- p. 153-158.
Conference
- Title
- 10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
- Dates
- 14-18 Aug 1989.
- Place
- Anaheim, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21080184
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT; DYNAMIC LOADS; HAZARDS; PHWR TYPE REACTORS; REACTOR SAFETY; RUPTURES; STEAM LINES
- Descriptors DEC
- FAILURES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; PIPELINES; REACTORS; SAFETY
Optional Information
- Secondary number(s)
- CONF-890855--.