Published 2006
| Version v1
Book
Fission product release from nuclear fuel under accident conditions - computer codes and their validations
Creators
- 1. Planning and Coordination Div., Bhabha Atomic Research Centre, Mumbai (India)
Description
The present paper intends to discuss the important features and methodologies of modeling the fission product releases from the fuel under accident conditions, adopted by different computer codes and their validations against test data and current state-of-the-art in BARC
Additional details
Publishing Information
- Publisher
- Board of Research in Nuclear Sciences
- Imprint Place
- Mumbai (India)
- Imprint Title
- Fuel behaviour under accident conditions: proceedings of theme meeting
- Imprint Pagination
- 79 p.
- Journal Page Range
- p. 18-25
Conference
- Title
- 3. high burnup issues in nuclear fuels
- Acronym
- HBINF-2005
- Dates
- 24 Mar 2006
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 37098767
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; DESIGN BASIS ACCIDENTS; FISSION PRODUCT RELEASE; NUCLEAR POWER PLANTS; O CODES; PHWR TYPE REACTORS; VALIDATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTORS; TESTING; THERMAL POWER PLANTS
Optional Information
- Notes
- 30 ills.