Published 1987
| Version v1
Book
A multi-step approach for evaluation of pipe impact effects
Description
A flexible procedure was developed for evaluation of interactions resulting from postulated high-energy line breaks inside containment. The procedure includes steps of increasing sophistication. It starts with inexpensive energy dissipation assessments for very safe interactions and proceeds to 3-D non-linear dynamic analyses when warranted. The simplest approaches allowed qualification of 80% of interactions at Garona NPP. The implementation of the procedures proposed here, combined with detail safety analyses of the plant, permitted qualifying all resulting interactions without imposing plant design changes
Additional details
Publishing Information
- Publisher
- A.A. Balkema Publishers.
- Imprint Place
- Accord, MA (USA)
- ISBN
- 90-6191-767-0
- Imprint Title
- Structural mechanics in reactor technology
- Journal Page Range
- p. 115-120.
Conference
- Title
- 9. biennial international conference on structural mechanics in reactor technology (SMIRT-9).
- Dates
- 17-21 Aug 1987.
- Place
- Lausanne (Switzerland).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19055555
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; BREAKDOWN; DISSIPATION FACTOR; DYNAMIC LOADS; EVALUATION; IMPACT STRENGTH; IMPACT TESTS; NONLINEAR PROBLEMS; NUCLEAR POWER PLANTS; PIPES; REACTOR SAFETY EXPERIMENTS; SPECIFICATIONS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; NUCLEAR FACILITIES; POWER PLANTS; TESTING; THERMAL POWER PLANTS