Published September 1984
| Version v1
Book
Stress distribution around the equipment hatch opening of a prestressed concrete containment for a PWR power station
Creators
- 1. Nuclear Safety Technology Branch, Safety and Reliability Directorate, United Kingdom Atomic Energy Authority, Wigshaw Lane, Culcheth, Warrington, Cheshire
Description
The authors report here the results of a finite element stress analysis for the linear elastic deformation around the equipment hatch opening in a prestressed concrete containment. The dimensions and form of the containment are taken to be representative of current design practice for the primary containment of a PWR power station; however the study is generic. Of particular interest is the response of the containment to beyond design-basis load levels. To this end results are included which involve over-load pressurization together with an approximate treatment of the propagation and stability of cracks in the concrete around the equipment hatch opening
Additional details
Publishing Information
- Publisher
- A.S.C.E.
- Imprint Place
- New York, NY (USA)
- Imprint Title
- Structural engineering in nuclear facilities, vol. 2
- Journal Page Range
- p. 828-846.
Conference
- Title
- Conference on structural engineering in operating nuclear facilities.
- Dates
- 10-12 Sep 1984.
- Place
- Raleigh, NC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16061563
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SYSTEMS; CRACK PROPAGATION; DEFORMATION; DISTRIBUTION; DYNAMIC LOADS; ELASTICITY; FINITE ELEMENT METHOD; FRACTURE PROPERTIES; MECHANICAL TESTS; OPENINGS; PRESSURIZATION; PRESTRESSED CONCRETE; PWR TYPE REACTORS; SPECIFICATIONS; STRESS ANALYSIS; STRESS INTENSITY FACTORS; STRESSES
- Descriptors DEC
- BUILDING MATERIALS; COMPOSITE MATERIALS; CONCRETES; CONTAINMENT; ENRICHED URANIUM REACTORS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS