Published May 2002
| Version v1
Miscellaneous
The effect of thermal conductivity on the DUPIC fuel behavior
Description
The thermal conductivity model of DUPIC fuel was proposed based on the experimental data obtained from reference simulated DUPIC fuel. Using the modified CANDU fuel performance code, the thermal behavior of DUPIC fuel was estimated under the conditions of the nominal design power envelope and high power envelope. These results were compared with the behavior of UO2 fuel under the same conditions. Also, the estimated data of the centerline temperature and fission gas release volume of DUPIC fuel were compared with the post- irradiation examination data, and the conservative meeting point was observed
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS-KARP Joint spring meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [7 p.]
Conference
- Title
- 2002 joint spring meeting of the KNS-KARP
- Dates
- 23-24 May 2002
- Place
- Gwangju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 34009833
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; DESIGN; EXPERIMENTAL DATA; FISSION PRODUCT RELEASE; POST-IRRADIATION EXAMINATION; SPENT FUELS; THERMAL CONDUCTIVITY; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; DATA; ENERGY SOURCES; FUELS; HEAVY WATER MODERATED REACTORS; INFORMATION; MATERIALS; NUCLEAR FUELS; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 11 refs, 6 figs