Reliability evaluation of the safety service cooling water system of Angra 2 under external events
- 1. Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE). Programa de Engenharia Nuclear
- 2. Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao de Reatores (CODRE)
Description
This work evaluates the reliability of the Safety Service Cooling Water System (PE) of Angra 2, taking into account the current structure of the system. The fault tree analysis was the method used to identify the main failures of the system emergency cooling pumps, which must start operating under external event conditions (EVA). A system design modification was considered, and a new evaluation of the system reliability was carried out. Such modification is based on the reduction effects of the number of the system components. The aim of this modification is to optimize the system performance, without violating its safety criteria. Then, the fault tree quantification results of the analyzed structures were compared. Finally, from the reliability point of view, it can be concluded that the proposed modification is viable and does not violate the regulatory safety demands. (author)
Additional details
Publishing Information
- ISBN
- 978-85-99141-02-1
- Imprint Title
- Proceedings of the INAC 2007 International nuclear atlantic conference. Nuclear energy and energetic challenges for 21st. century. 15. Brazilian national meeting on reactor physics and thermal hydraulics; 8. Brazilian national meeting on nuclear applications
- Imprint Pagination
- [vp.]
- Journal Page Range
- [6 p.]
Conference
- Title
- INAC 2007 International nuclear atlantic conference. Nuclear energy and energetic challenges for 21st. century. 15. Brazilian national meeting on reactor physics and thermal hydraulics; 8. Brazilian national meeting on nuclear applications
- Dates
- 30 Sep - 5 Oct 2007
- Place
- Santos, SP (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 39084814
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- ANGRA-2 REACTOR; EXPERIMENTAL DATA; FAULT TREE ANALYSIS; PROBABILISTIC ESTIMATION; PUMPS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RELIABILITY; WATER
- Descriptors DEC
- CALCULATION METHODS; COOLING SYSTEMS; DATA; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; HYDROGEN COMPOUNDS; INFORMATION; NUMERICAL DATA; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs., 2 figs., 1 tab. Code: R04_886.pdf