Published 1984 | Version v1
Book Metadata-only

Important plant design and operational features for internally initiated accident sequences

Creators

  • 1. Sandia National Lab., Albuquerque, NM

Description

Several recent efforts have been made at Sandia National Laboratories to review and evaluate the existing Probabilistic Risk Assessment (PRA) information base to determine which plant design and operational features have the greatest potential for dominating the likelihood of occurrence of internally initiated core melt sequences. This paper presents results from two of these programs in terms of potentially important accident sequences, systems, components, and operational features

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (USA)
Imprint Title
Proceedings of international nuclear power plant thermal hydraulics and operations topical meeting
Journal Page Range
p. I2-1-I2-7.

Conference

Title
International thermal hydraulics and plant operations topical meeting.
Dates
22-24 Oct 1984.
Place
Taipei, TW (China).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17069231
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
MELTDOWN; POWER REACTORS; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR OPERATION; REACTOR SAFETY; RISK ASSESSMENT; SPECIFICATIONS; SYSTEMS ANALYSIS
Descriptors DEC
ACCIDENTS; OPERATION; REACTORS; SAFETY