Published 1997
| Version v1
Miscellaneous
Study on the importance and sensibility of the parameters used in the Angra-1 auxiliary feedwater system reliability analysis
Creators
- 1. Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil)
- 2. Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia
Description
In this paper some procedures are presented in order to develop an importance and sensitivity analysis on the parameters considered in the reliability study of the Auxiliary Feedwater System of Angra-1. The importance analysis is performed to determine the events which have contribution on the top event. The results obtained from the sensitivity analysis can show the effects of variations in probability values of the dominant component failures on the probability of the top event. (author). 7 refs., 9 figs., 5 tabs
Additional details
Additional titles
- Original title (Portuguese)
- Estudo da importancia e sensibilidade dos parametros utilizados na analise da confiabilidade do sistema de agua de alimentacao auxiliar de Angra-1
Publishing Information
- Imprint Title
- Proceedings of the 11. ENFIR: Meeting on reactor physics and thermal hydraulics
- Imprint Pagination
- 838 p.
- Journal Page Range
- p. 628-633.
Conference
- Title
- Meeting on reactor physics and thermal hydraulics.
- Acronym
- 11. ENFIR
- Dates
- 18-22 Aug 1997.
- Place
- Pocos de Caldas, MG (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 28075976
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ANGRA-1 REACTOR; FEEDWATER; NUCLEAR ENGINEERING; PARAMETRIC ANALYSIS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR TECHNOLOGY; REACTORS; RELIABILITY; RISK ASSESSMENT; SENSITIVITY ANALYSIS; SYSTEMS ANALYSIS
- Descriptors DEC
- COOLING SYSTEMS; ENGINEERING; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; SAFETY; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Joint nuclear conference with the 4. ENAN: Brazilian meeting on nuclear applications.