Unavailability of the residual system heat removal of Angra 1 by Bayesian networks considering dependent failures
Creators
- 1. Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Programa de Pos-Graduacao em Engenharia Nuclear
Description
This work models by Bayesian networks the residual heat removal system (SRCR) of Angra I nuclear power plant, using fault tree mapping for systematically identifying all possible modes of occurrence caused by a large loss of coolant accident (large LOCA). The focus is on dependent events, such as the bridge system structure of the residual heat removal system and the occurrence of common-cause failures. We used the Netica™ tool kit, Norsys Software Corporation and Python 2.7.5 for modeling Bayesian networks and Microsoft Excel for modeling fault trees. Working with dependent events using Bayesian networks is similar to the solutions proposed by other models, beyond simple understanding and ease of application and modification throughout the analysis. The results obtained for the unavailability of the system were satisfactory, showing that in most cases the system will be available to mitigate the effects of an accident as described above. (author)
Files
46135927.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- INIS-BR--15698
Conference
- Title
- international nuclear atlantic conference. Brazilian nuclear program. State policy for a sustainable world; 4. ENIN: meeting on nuclear industry
- Acronym
- INAC 2015
- Dates
- 4-9 Oct 2015
- Place
- Sao Paulo, SP (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 46135927
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENT MANAGEMENT; ANGRA-1 REACTOR; ECCS; FAILURES; FAULT TREE ANALYSIS; LOSS OF COOLANT; RHR SYSTEMS; SAFETY
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; MANAGEMENT; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS