Published 1976
| Version v1
Report
Open
GAP-1 - a computer program to predict pellet clad gap conductance in nuclear fuels
Creators
- 1. Bhabha Atomic Research Centre, Bombay (India). Reactor Engineering Div.
Description
GAP-1, a digital computer (BESM-6) program for the evaluation of pellet cladding gap conductance in zircaloy clad-UO2 fuels is described. It takes into account pellet and clad thermal expansion, pellet relocation, irradiation swelling and fission gas release and dilution of filler gas. The typical results obtained for a BWR fuel are given. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
8313633.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- INIS-mf--3476
Conference
- Title
- 3. national heat and mass transfer conference.
- Dates
- 11 Dec 1975.
- Place
- Bombay, India.
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 8313633
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; FISSION PRODUCTS; FUEL CANS; FUEL PELLETS; G CODES; GASES; PHYSICAL RADIATION EFFECTS; SWELLING; THERMAL CONDUCTION; THERMAL EXPANSION; URANIUM DIOXIDE; ZIRCALOY
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOYS; CHALCOGENIDES; COMPUTER CODES; DEFORMATION; ENERGY TRANSFER; EXPANSION; FLUIDS; HEAT TRANSFER; ISOTOPES; OXIDES; OXYGEN COMPOUNDS; RADIATION EFFECTS; RADIOACTIVE MATERIALS; REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 17 refs.