Development of CANDU advanced fuel bundle
Creators
- 1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Description
This research project is underway in cooperation with AECL to develop the CANDU advanced fuel bundle (so-called, CANFLEX) which can enhance reactor safety and fuel economy in comparison with the current CANDU fuel and which can be used with natural uranium, slightly enriched uranium and other advanced fuel cycle. As the final schedule, the advanced fuel will be verified by carrying out a large scale demonstration of the bundle irradiation in a commercial CANDU reactor for 1996 and 1997, and consequently will be used in the existing and future CANDU reactors in Korea. The research activities during this year include the detail design of CANFLEX fuel with natural enriched uranium (CANFLEX-NU). Based on this design, CANFLEX fuel was mocked up. Out-of-pile hydraulic scoping tests were conducted with the fuel in the CANDU Cold Test Loop to investigate the condition under which maximum pressure drop occurs and the maximum value of the bundle pressure drop. (Author)
Availability note (English)
MF available from INIS under the Report Number.Files
24057332.pdf
Files
(10.5 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 356 p.
- Report number
- KAERI/RR--1119/91
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 24057332
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CANDU TYPE REACTORS; COMPUTER CODES; DESIGN; FUEL ELEMENT CLUSTERS; HYDRAULICS; PRESSURE DROP; REACTOR CORES; THERMAL NEUTRONS; THERMODYNAMICS
- Descriptors DEC
- BARYONS; ELEMENTARY PARTICLES; FERMIONS; FUEL ASSEMBLIES; HADRONS; HEAVY WATER MODERATED REACTORS; NEUTRONS; NUCLEONS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS