Published 1986 | Version v1
Miscellaneous Metadata-only

Frequency probabilistic analysis of a small break LOCA due to a power operated relief valve (PORV) for Angra-1 pre-TMI and post-TMI

Creators

  • 1. FURNAS, Rio de Janeiro (Brazil)

Description

After the TMI event efforts were aimed towards improvements in the operational and administrative procedures related to the power operated relief valves (PORVs) in order to decrease the probability of a small-break loss-of-coolant accident (LOCA) caused by stuck-open power operated relief valve. This paper presents a frequency probabilistic analysis of a small break LOCA due to a stuck open PORV and safety valve to the Angra I nuclear power plant in operating conditions pre-TMI and post-TMI. (Author)

Abstract (Portuguese)

Apos o acidente de TMI houve uma preocupacao em melhorar os aspectos operacionais e administrativos das valvulas de alivio do pressurizador (PORVs) a fim de diminuir os riscos de as mesmas falharem abertas. Neste trabalho apresentamos uma analise probabilistica de frequencia de pequeno LOCA pela PORV e valvula de seguranca para Angra I em condicoes operacionais pre e pos-TMI. (Autor)

Additional details

Additional titles

Original title (Portuguese)
Analise probabilistica de frequencia de pequenos LOCA pela PORV para Angra 1 pre-TMI e pos-TMI

Publishing Information

Imprint Title
Proceedings of the 1. General Congress of Nuclear Energy. v. 1
Imprint Pagination
430 p.
Journal Page Range
v. 1 p. 14-17.
Report number
INIS-BR--537(v.1)

Conference

Title
1. General Congress of Nuclear Energy.
Dates
17-20 Mar 1986.
Place
Rio de Janeiro, RJ (Brazil).

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
17069455
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANGRA-1 REACTOR; FAULT TREE ANALYSIS; LOSS OF COOLANT; PRESSURIZERS; VALVES
Descriptors DEC
ACCIDENTS; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

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