Published 1989
| Version v1
Book
The strain behavior of prestressed concrete reactor pressure vessels over 20 years operation
Description
This paper is based on work in support of a statutory long term safe review (LTSR) prepared, to validate the integrity of a nuclear plant for an operational life of up to 30 years. The R1 vessel strain behavior is updated and reassessed, and data for R2 vessel is included. These regular results were obtained primarily with the vessels pressurized
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
- 257 p.
- Series
- Concrete structures.
- Journal Page Range
- p. 179-184.
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
- 21076241
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- MAGNOX TYPE REACTORS; PRESSURIZATION; PRESTRESSED CONCRETE; REACTOR MONITORING SYSTEMS; REACTOR SAFETY; REACTOR VESSELS; STRAIN GAGES; STRAINS; STRESS ANALYSIS
- Descriptors DEC
- BUILDING MATERIALS; COMPOSITE MATERIALS; CONCRETES; CONTAINERS; MATERIALS; MEASURING INSTRUMENTS; NATURAL URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY
Optional Information
- Secondary number(s)
- CONF-890855--.