Published October 1998
| Version v1
Miscellaneous
Preliminary nuclear design for test MOX fuel rods
- 1. KAERI, Taejon (Korea, Republic of)
Description
A preliminary neutronic evaluation for the test fuel was performed to determine the fuel rod position in the rig and to assure the achievement of target linear power and burnup. Since the fuel rod positions in the test fuel assembly do not affect the rod power distribution, the position of the test fuel rods in the rig was determined mainly from the consideration of instrumentation device installation. In order to achieve target linear power and burnup of the test fuel rods, the test fuel assembly rig needs to be loaded for at least 750EFPDs in core periphery where the driver fuel assembly produces the power of about 130kW
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the Korean Nuclear Society autumn meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [8 p.]
Conference
- Title
- 1998 autumn meeting of the Korean Nuclear Society
- Dates
- 30-31 Oct 1998
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 32066898
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; DESIGN; EVALUATION; FUEL ASSEMBLIES; FUEL RODS; IRRADIATION CAPSULES; NUCLEAR FUELS
- Descriptors DEC
- ENERGY SOURCES; FUEL ELEMENTS; FUELS; MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS
Optional Information
- Notes
- 1 ref, 9 figs, 2 tabs