Published July 1992 | Version v1
Report Metadata-only

SBWR reinforced concrete containment structural performance during severe accident

Creators

  • 1. ENEA-Disp, Rome (Italy)

Description

The Simplified Boiling Water Reactor (SBWR) reinforced concrete containment structure is analyzed for its ultimate internal pressure capability under slow pressurization and the associated temperature loads in case of severe accident. In the first phase of the analysis an axisymmetric Finite Element model has been considered with an increasing internal pressure without temperature effects; in the second phase a temperature transient load has been applied to the structure before pressurization. Major topics of the performed analysis have been addressed, with emphasis on the failure criteria applicable to reinforced concrete structure

Additional details

Publishing Information

Imprint Title
Proceedings of the fifth workshop on containment integrity
Imprint Pagination
646 p.
Journal Page Range
p. 191-226.
Report number
NUREG/CP--0120

Conference

Title
5. workshop on containment integrity for nuclear power plants.
Dates
12-14 May 1992.
Place
Washington, DC (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24027156
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; COMPRESSION STRENGTH; CONTAINMENT SYSTEMS; CRACKS; DESIGN; DYNAMIC LOADS; ELECTRIC UTILITIES; FAILURES; FINITE ELEMENT METHOD; LINERS; MECHANICAL PROPERTIES; PRESSURIZATION; REACTOR ACCIDENTS; REACTOR SAFETY; REINFORCED CONCRETE; RELIABILITY; STANDARDIZATION; TEMPERATURE DEPENDENCE; TEMPERATURE DISTRIBUTION; TRANSIENTS
Descriptors DEC
ACCIDENTS; BUILDING MATERIALS; CALCULATION METHODS; COMPOSITE MATERIALS; CONCRETES; CONTAINMENT; ELECTRIC POWER INDUSTRY; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; INDUSTRY; MATERIALS; NUMERICAL SOLUTION; POWER REACTORS; PUBLIC UTILITIES; REACTORS; REINFORCED MATERIALS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
SAND--92-0173; CONF-920541--.