Published November 2005
| Version v1
Book
A model for calculation of fission gas release from restructuring observed in fuel
Creators
- 1. Post Irradiation Examination Div., Bhabha Atomic Research Centre, Mumbai (India)
Description
A method has been developed for estimating the fuel temperature and fission gas release fraction in a PHWR fuel pin using the fuel restructuring observed in the cross section of the irradiated fuel. This method has been applied to estimate the maximum fuel center temperature experienced by the fuel during irradiation and fission gas release in the fuel pins of a PHWR fuel bundle irradiated to a high burn-up. The radial profile of retained fission gas in the pellet has been calculated and compared with the fission product distribution observed in beta gamma auto-radiograph of the fuel. Calculated fission gas release and retained gas radial profile show good match with experimental observations. (author)
Additional details
Publishing Information
- Publisher
- Indian Nuclear Society
- Imprint Place
- Mumbai (India)
- Imprint Title
- Sixteenth annual conference of Indian Nuclear Society: science behind nuclear technology
- Imprint Pagination
- [1063 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- 16. annual conference of Indian Nuclear Society
- Acronym
- INSAC-2005
- Dates
- 15-18 Nov 2005
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 37061870
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; FISSION PRODUCT RELEASE; FUEL ELEMENT CLUSTERS; FUEL PINS; GAMMA RADIOGRAPHY; PHWR TYPE REACTORS
- Descriptors DEC
- FUEL ASSEMBLIES; FUEL ELEMENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INDUSTRIAL RADIOGRAPHY; MATERIALS TESTING; NONDESTRUCTIVE TESTING; REACTOR COMPONENTS; REACTORS; TESTING
Optional Information
- Notes
- 2 refs., 4 figs., 1 tab.