Proceedings of the fifth workshop on containment integrity
Conference
·
OSTI ID:10170502
- eds.; Sandia National Labs., Albuquerque, NM (United States)
The Fifth Workshop on Containment integrity was held in Washington, DC, on May 12--14, 1992. The purpose of these workshops is to provide an international forum for the exchange of information on performance of containments in nuclear power plants under severe accident loadings. Severe accident investigations of existing containment designs as well as future advanced containments were presented during the workshop. There were 145 participants at the workshop from 15 countries. Individual papers have been cataloged separately.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 10170502
- Report Number(s):
- NUREG/CP-0120; SAND-92-0173; CONF-920541-; ON: TI92019298
- Resource Relation:
- Conference: Fifth Workshop on Containment Integrity held May 12-14, 1992 in Washington, D.C.; Other Information: PBD: Jul 1992
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT SYSTEMS
PWR TYPE REACTORS
NUCLEAR POWER PLANTS
REACTOR ACCIDENTS
FISSION PRODUCT RELEASE
REACTOR MATERIALS
CONTAINMENT SHELLS
TESTING
AGING
HYDROGEN
IN-SERVICE INSPECTION
LEADING ABSTRACT
COMPUTER CODES
220900
210100
210200
220502
REACTOR SAFETY
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
RADIOACTIVE EFFLUENTS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT SYSTEMS
PWR TYPE REACTORS
NUCLEAR POWER PLANTS
REACTOR ACCIDENTS
FISSION PRODUCT RELEASE
REACTOR MATERIALS
CONTAINMENT SHELLS
TESTING
AGING
HYDROGEN
IN-SERVICE INSPECTION
LEADING ABSTRACT
COMPUTER CODES
220900
210100
210200
220502
REACTOR SAFETY
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
RADIOACTIVE EFFLUENTS