Published 1978 | Version v1
Miscellaneous Open

Loss of coolant accident. Past, present and future

Creators

  • 1. Westinghouse Electric Corp., Pittsburgh, PA (USA)

Description

The history of LOCA is covered from the original design basis, failure of the largest connecting pipe with no peak clad temperature limit through to the current design basis, double ended failure of the largest pipe in the primary system with a design peak clad temperature limit of 22000F. Various obstacles along the way are addressed such as, degree of analytical sophisticaton, perplexing experimental results, the infamous 1971 semiscale tests, fuel densification and changes in USNRC evaluation models. In the future, it is projected that more reliance will be put on probabilistic evaluation of the LOCA with respect to both the accident analysis, reliability of the system and the probability of the accident itself. (author)

Availability note (English)

MF available from INIS under the Report Number.

Files

10469902.pdf

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Additional details

Publishing Information

Imprint Pagination
10 p.
Report number
INIS-mf--5071

Conference

Title
ENS/ANS international topical meeting on nuclear power reactor safety.
Dates
16 - 19 Oct 1978.
Place
Brussels, Belgium.

INIS

Country of Publication
Belgium
Country of Input or Organization
Belgium
INIS RN
10469902
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ECCS; HEAT TRANSFER; LOSS OF COOLANT; REVIEWS; RISK ANALYSIS; WATER COOLED REACTORS
Descriptors DEC
ACCIDENTS; DOCUMENT TYPES; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS

Optional Information

Notes
1 ref.