Published November 2002
| Version v1
Book
Assessment of fission product release rates using the code CORSOR for the 220 MWe Indian PHWRs under a severe accident scenario
- 1. Reactor Safety Div., Bhabha Atomic Research Centre, Mumbai (India)
Description
Full text: The assessment of release of radioactivity from within the reactor core into the primary heat transport (PHT) system, in the form of fission product aerosols, is the first step in the overall exercise of estimating the source term for nuclear power plants. The computer code CORSOR is widely used for this purpose. This code has been used in BARC also for the assessment of fission product release rates under accident conditions. This paper briefly describes the code CORSOR along with its release models and the studies performed to estimate the fission product release rates for a postulated severe accident sequence in our reactors. The results obtained for this accident sequence are also presented
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. 359
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
- 34011447
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; ENVIRONMENTAL EFFECTS; FISSION PRODUCTS; PHWR TYPE REACTORS; PRIMARY COOLANT CIRCUITS; REACTOR CORES; REACTOR SAFETY
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; ISOTOPES; MATERIALS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY