Published 1992 | Version v1
Miscellaneous Metadata-only

Best estimate calculation methodology for nuclear power plants loss of coolant accident analysis

Creators

  • 1. Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

Description

Recent experimental results led to a better knowledge of the physical phenomena in Loss of Coolant Accidents (LOCA). The LOCA analysis methodologies showed great conservatism margin, which led to the development of new computer codes with realistic models. For Nuclear Power Plant (NPP) licensing purposes these new codes must have their uncertainties determined. Because of that, the USNRC developed the CSAU methodology and CNEN's independent calculation procedure to safety review of NPP's. (author)

Additional details

Additional titles

Original title (Portuguese)
Metodologia de calulo de melhor estimativa para analise de acidentes de perda de refrigerante em usinas nucleares

Publishing Information

Imprint Title
Proceedings of the 4. General Congress on Nuclear Energy. v. 1
Imprint Pagination
496 p.
Journal Page Range
p. 59-64.

Conference

Title
4. General Congress on Nuclear Energy.
Dates
5-9 Jul 1992.
Place
Rio de Janeiro, RJ (Brazil).

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
23079320
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BRAZILIAN CNEN; C CODES; COMPUTERIZED SIMULATION; LOSS OF COOLANT; PWR TYPE REACTORS; SAFETY
Descriptors DEC
ACCIDENTS; BRAZILIAN ORGANIZATIONS; COMPUTER CODES; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:Anais do 4. Congresso Geral de Energia Nuclear. v. 1.