Published November 1988 | Version v1
Report Metadata-only

Proving Test on the Reliability for Reactor Containment Vessel

Creators

  • 1. Nuclear Power Engineering Test Center, Tokyo (Japan)

Description

NUPEC (Nuclear Power Engineering Test Center) has started an eight-year project of Proving Test on the Reliability for Reactor Containment Vessel since June 1987. The objective of this project is to confirm the integrity of containment vessels under severe accident conditions. This paper shows the outline of this project. The test Items are (1) Hydrogen mixing and distribution test, (2) Hydrogen burning test, (3) Iodine trapping characteristics test, and (4) Structural behavior test. Based on the test results, computer codes are verified and as the results of analysis and evaluation by the computer codes, containment integrity is to be confirmed

Additional details

Publishing Information

Imprint Title
Fourth workshop on containment integrity. Proceedings
Imprint Pagination
656 p.
Journal Page Range
p. 231-242.
Report number
NUREG/CP--0095

Conference

Title
4. workshop on integrity of containments for nuclear power plants.
Dates
14-17 Jun 1988.
Place
Arlington, VA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21068143
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; COMBUSTION; COMPUTER CODES; CONTAINMENT BUILDINGS; CONTAINMENT SYSTEMS; FILTRATION; HYDROGEN; IODINE; JAPAN; MECHANICAL PROPERTIES; MITIGATION; MIXING; NUCLEAR POWER PLANTS; PRESSURIZATION; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; RELIABILITY; RESEARCH PROGRAMS; SCALE MODELS; TEST FACILITIES
Descriptors DEC
ACCIDENTS; ASIA; BUILDINGS; CHEMICAL REACTIONS; CONTAINMENT; DEVELOPED COUNTRIES; ELEMENTS; ENRICHED URANIUM REACTORS; HALOGENS; NONMETALS; NUCLEAR FACILITIES; OXIDATION; POWER PLANTS; POWER REACTORS; REACTORS; SAFETY; SEPARATION PROCESSES; STRUCTURAL MODELS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
SAND--88-1836; CONF-880616--.