Fire PSA for MAPS
- 1. Reactor Safety Div., Bhabha Atomic Research Centre, Mumbai (India)
Description
Full text: Fire hazard has been identified as one of the major contributors to a plant's operational risk. As a result of several fire incidences at nuclear power plants, internal fire is included in level 1 probabilistic safety assessment (PSA) studies of nuclear power plants (NPPs). This activity is termed as fire risk analysis or fire PSA. In this context, fire PSA studies were initiated for Madras Atomic Power Station (MAPS). Fire PSA extends the consequence analysis of a fire event towards core damage, in case of nuclear power plants. The paper summarises and gives an overview of the fire PSA procedure performed for MAPS. It highlights the issues associated with the collection of data and information needed for fire modelling. An estimate of the contribution of fire to core damage frequency (CDF) has been obtained
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- First national conference on nuclear reactor technology
- Imprint Pagination
- 421 p.
- Journal Page Range
- p. 327
Conference
- Title
- 1. nuclear reactor safety
- Acronym
- NRT-1
- Dates
- 25-27 Nov 2002
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 34011393
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FIRES; KALPAKKAM-1 REACTOR; KALPAKKAM-2 REACTOR; PROBABILISTIC ESTIMATION; REACTOR CORES; REACTOR OPERATION; REACTOR SAFETY; SAFETY ANALYSIS
- Descriptors DEC
- HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; OPERATION; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY