Published 1995
| Version v1
Journal article
Aging in the probabilistic safety analysis of Laguna Verde Nuclear Power Plant
Creators
- 1. Comision Nacional de Seguridad Nuclear y Salvaguardias, Mexico City (Mexico)
Description
To put into effect a probabilistic safety analysis which depends on the aging of equipment and components considered, fault rates dependent of the age are required. In order to optimize the incorporation of the aging to a probabilistic safety analysis, relative aging rates associated to the type of components are used. Is inside this context that linear approximation to the fault rates dependent to time are made, to infer the relative aging rates, applying with this the aging factors to the basic fault events which are related with the type of components considered for this study. Then is found the dependence of the frequency of core damage (FCD) with respect to the age of the type of components. (Author)
Additional details
Additional titles
- Original title (Spanish)
- Envejecimiento en el APS de la CNLV
Publishing Information
- Journal Title
- Mexico Nuclear
- Journal Volume
- 1
- Journal Issue
- 1
- Journal Page Range
- p. 10-14.
- CODEN
- MENUFK
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 27031975
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- AGING; DIESEL ENGINES; LAGUNA VERDE-1 REACTOR; LINEAR PROGRAMMING; PROBABILISTIC ESTIMATION; REACTOR CORES; REACTOR MAINTENANCE; RISK ASSESSMENT; SAFETY ANALYSIS; TURBOMACHINERY; VALVES
- Descriptors DEC
- BWR TYPE REACTORS; CONTROL EQUIPMENT; ENGINES; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; HEAT ENGINES; INTERNAL COMBUSTION ENGINES; MACHINERY; MAINTENANCE; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS