Published 1995
| Version v1
Book
Dynamic response of a containment surrounding extreme pressure source due to steam explosion
- 1. Kawasaki Heavy Industries Ltd., Tokyo (Japan). Nuclear Systems Div.
- 2. Japan Atomic Energy Research Inst., Ibaraki (Japan)
Description
Based on the results of measurement of steam in a high-temperature high -pressure region (hereinafter referred to as a source) generated during steam explosion experiments, analytic models were developed, and such models showed possibility of reproducing those experiments. The energetic level of the source and structure of the containment vessel were subjected to parametric analyses with the help of the analytic models, and attention was paid to the mechanism of pressure wave propagation so as to understand the load applied to a containment vessel. (author). 6 refs., 12 figs., 2 tabs
Additional details
Publishing Information
- Publisher
- Editora da Universidade Federal do Rio Grande do Sul.
- Imprint Place
- Porto Alegre, RS (Brazil)
- ISBN
- 85-7025-351-6
- Imprint Title
- Transactions of the 13. International conference on structural mechanics in reactor technology. v. 4
- Imprint Pagination
- 860 p.
- Journal Page Range
- p. 359-370.
Conference
- Title
- 13. International conference on structural mechanics in reactor technology.
- Dates
- 13-18 Aug 1995.
- Place
- Porto Alegre, RS (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 28061626
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONCRETES; CONTAINMENT; CONTAINMENT BUILDINGS; DYNAMIC LOADS; MECHANICAL PROPERTIES; NUCLEAR ENGINEERING; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR TECHNOLOGY; REACTOR VESSELS; REACTORS; STEAM; STRESS ANALYSIS; STRESSES
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; BUILDINGS; CONTAINERS; ENGINEERING; MATERIALS; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; THERMAL POWER PLANTS
Optional Information
- Notes
- Imprint:Conference organized by the International Association for Structural Mechanis in Reactor Technology and Universidade Federal do Rio Grande do Sul.