Published 1989 | Version v1
Miscellaneous Metadata-only

Realistic analysis of steam generator tube rupture accident in Angra-1 reactor

Creators

  • 1. FURNAS, Rio de Janeiro, RJ (Brazil)

Description

This paper presents the analysis of different scenarios for a Steam Generator Tube Rupture accident (SGTR) in Angra-1 NPP. The results and conclusions will be used as support in the preparation of the emergency situation programs for the plant. For the analysis a SGTR simulation was performed with RETRAN-02 code. The results indicated that the core integrity and the plant itself will not affect by small ruptures in SG tubes. For large ruptures the analysis demonstrated that the accident may have harmful consequences if the operator do not actuate effectively since the initial moments of the accidents. (author)

Availability note (English)

Available from the Library of Comissao Nacional de Energia Nuclear, RJ, Brazil.

Abstract (Portuguese)

Neste trabalho apresenta-se uma analise de varios cenarios de acidente de ruptura de tubos do gerador de vapor (RTGV) em Angra-1, com a usina em controle automatico apenas. Os resultados e conclusoes desta analise serao importantes nos programas de preparacao da usina para situacoes de emergencia. A analise foi realizada tendo como base a simulacao termohidraulica de uma RTGV, utilizando-se o programa de calculo RETRAN-02. Os resultados mostram que, no caso de pequenas rupturas de tubos, nao sao previstas consequencias graves para o reator e a usina em geral, mesmo no caso de perda de alimentacao eletrica para a usina. No caso de grandes rupturas de tubos, a analise mostra que o acidente pode ter graves consequencias, caso o operator da usina nao atue de forma efetiva, ja nos instantes iniciais do acidente. (autor)

Additional details

Additional titles

Original title (Portuguese)
Analise realistica do acidente de ruptura de tubos do gerados de vapor de Angra-1

Publishing Information

Imprint Title
Proceedings of the 7. National Meeting of Reactor Physics and Thermohydraulic. v. 2
Imprint Pagination
358 p.
Journal Page Range
p. 125-136.

Conference

Title
7. National Meeting of Reactor Physics and Thermohydraulic.
Dates
26-28 Apr 1989.
Place
Recife, PE (Brazil).

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
20061084
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ANGRA-1 REACTOR; COMPUTER CALCULATIONS; R CODES; REACTOR ACCIDENTS; RUPTURES; STEAM GENERATORS; THERMAL ANALYSIS; TUBES
Descriptors DEC
ACCIDENTS; BOILERS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:Anais do 7. Encontro Nacional de Fisica de Reatores e Termohidraulica. v. 2.