CNE (central nuclear en Embalse): probabilistic safety study. Loss-of-coolant accidents. Analysis through events sequence
Creators
- 1. Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Gerencia de Ingenieria
Description
The aim of this study was to perform for the Embalse nuclear power plant, a probabilistic evaluation of loss-of-coolant accidents (LOCA) to identify the risks associated with them and to determine their acceptability in accordance with norms. This study includes all ruptures in the primary system that produce the automatic activation of 'emergency core cooling system'. Three starting events were selected for the probabilistic evaluation: 100% rupture of an input collector; 5% rupture of an input collector; 1.2% rupture of an input collector. At this stage the evaluation is focussed on the identification and quantization of the main failure sequences that follow a LOCA and lead to an uncontrolled reactor state or 'core meltdown'. The most important contribution to the core meltdown due to LOCA is the failure of supplies that are required for the emergency core cooling system. (Author)
Files
24047799.pdf
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Additional details
Additional titles
- Original title (Spanish)
- CNE (central nuclear en Embalse): estudio probabilistico de seguridad. Accidentes con perdida de refrigerante primario. Analisis por secuencias de eventos
Publishing Information
- Publisher
- CNEA.
- Imprint Place
- Buenos Aires (Argentina)
- Imprint Title
- Proceedings of the fifteenth scientific meeting; fourth Latin American meeting; first sessions on nuclear power plants
- Imprint Pagination
- 735 p.
- Journal Page Range
- p. 576-580.
- Report number
- INIS-mf--12758
Conference
- Title
- 15. Scientific meeting; 4. Latin American meeting; 1. Sessions on nuclear power plants.
- Original Conference Title
- 15. Reunion cientifica
- Dates
- 2-6 Nov 1987.
- Place
- San Carlos de Bariloche (Argentina).
INIS
- Country of Publication
- Argentina
- Country of Input or Organization
- Argentina
- INIS RN
- 24047799
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN BASIS ACCIDENTS; EMBALSE REACTOR; FAULT TREE ANALYSIS; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; RADIATION ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR SAFETY; RUPTURES; SAFETY ANALYSIS; VAPOR GENERATORS
- Descriptors DEC
- ACCIDENTS; BOILERS; CANDU TYPE REACTORS; COOLING SYSTEMS; FAILURES; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS
Optional Information
- Notes
- Imprint:Actas de la decimoquinta reunion cientifica; cuarto encuentro latinoamericano; primeras jornadas sobre centrales nucleares.