Published 1995
| Version v1
Book
Finite element analysis of thermal stresses of the reactor vessel in a severe light water reactor accident
- 1. St. Petersburg State Technical Univ. (Russian Federation)
- 2. Research Inst. of Technology, Sosnovy Bor (Russian Federation)
Description
The thermal stress and damage analysis of the light water reactor (LWR) vessel is considered in a severe accident conditions. The high temperature corium accumulates on the vessel bottom and necessary condition of its holding is intensive cooling of vessel. External flooding with outside cooling of the LWR vessel is one of the accident management strategies being proposed to ensure the integrity of the vessel after a severe accident. (author). 8 refs., 5 figs
Additional details
Publishing Information
- Publisher
- Editora de Universidade Federal do Rio Grande do Sul.
- Imprint Place
- Porto Alegre, RS (Brazil)
- ISBN
- 85-7025-349-4
- Imprint Title
- Transactions of the 13. International Conference on Structural Mechanics in Reactor Technology. v. 1
- Imprint Pagination
- 604 p.
- Journal Page Range
- p. 123-128.
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
- 27029249
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CREEP; DYNAMIC LOADS; FAILURES; FINITE ELEMENT METHOD; FUEL ASSEMBLIES; FUEL ELEMENTS; FUELS; NUCLEAR FUELS; PRESSURE VESSELS; REACTOR COMPONENTS; REACTOR CORES; REACTOR SAFETY; REACTORS; STRESSES; THERMAL FRACTURES; THERMAL STRESSES; THERMOELASTICITY
- Descriptors DEC
- CALCULATION METHODS; CONTAINERS; ELASTICITY; ENERGY SOURCES; FRACTURES; MATERIALS; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; REACTOR MATERIALS; SAFETY
Optional Information
- Notes
- Imprint:Conference organized by the International Association for Structural Mechanics in Reactor Technology and Universidade Federal do Rio Grande do Sul.