Review of the severe accident risk reduction program (SARRP) containment event trees
Technical Report
·
OSTI ID:5830209
A part of the Severe Accident Risk Reduction Program, researchers at Sandia National Laboratories have constructed a group of containment event trees to be used in the analysis of key accident sequences for light water reactors (LWR) during postulated severe accidents. The ultimate goal of the program is to provide to the NRC staff a current assessment of the risk from severe reactor accidents for a group of five light water reactors. This review specifically focuses on the development and construction of the containment event trees and the results for containment failure probability, modes and timing. The report first gives the background on the program, the review criteria, and a summary of the observations, findings and recommendations. secondly, the individual reviews of each committee member on the event trees is presented. Finally, a review is provided on the computer model used to construct and evaluate the event trees.
- Research Organization:
- Wisconsin Univ., Madison (USA). Dept. of Nuclear Engineering
- OSTI ID:
- 5830209
- Report Number(s):
- NUREG/CR-4569; ON: TI86901464
- Country of Publication:
- United States
- Language:
- English
Similar Records
Containment event analysis for postulated severe accidents: Grand Gulf Nuclear Station, Unit 1
Containment event analysis for postulated severe accidents: Surry power station, Unit 1: Volume 1: Draft report for comment
Containment event analysis for postulated severe accidents: Sequoyah Power Station, Unit 1
Technical Report
·
Tue Mar 31 23:00:00 EST 1987
·
OSTI ID:6429462
Containment event analysis for postulated severe accidents: Surry power station, Unit 1: Volume 1: Draft report for comment
Technical Report
·
Sat Jan 31 23:00:00 EST 1987
·
OSTI ID:6658798
Containment event analysis for postulated severe accidents: Sequoyah Power Station, Unit 1
Technical Report
·
Sat Jan 31 23:00:00 EST 1987
·
OSTI ID:6614111
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BENCHMARKS
BWR TYPE REACTORS
CHEMICAL REACTIONS
COMBUSTION
CONTAINMENT
CONTAINMENT SYSTEMS
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
FAILURE MODE ANALYSIS
FAILURES
FISSION PRODUCT RELEASE
FREQUENCY ANALYSIS
HYDROGEN
MELTDOWN
NATIONAL ORGANIZATIONS
NONMETALS
OXIDATION
PRESSURIZING
PRIMARY COOLANT CIRCUITS
PROBABILITY
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMOCHEMICAL PROCESSES
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BENCHMARKS
BWR TYPE REACTORS
CHEMICAL REACTIONS
COMBUSTION
CONTAINMENT
CONTAINMENT SYSTEMS
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
FAILURE MODE ANALYSIS
FAILURES
FISSION PRODUCT RELEASE
FREQUENCY ANALYSIS
HYDROGEN
MELTDOWN
NATIONAL ORGANIZATIONS
NONMETALS
OXIDATION
PRESSURIZING
PRIMARY COOLANT CIRCUITS
PROBABILITY
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMOCHEMICAL PROCESSES
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS