Published 1987 | Version v1
Miscellaneous Open

Feasibility study on use of LEU [low enriched uranium] and MEU [medium enriched uranium] aluminide fuels in the KUR

  • 1. Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.

Description

Because of the delay of the safety review to use LEU silicide fuel in the KUR, the feasibility study on use of LEU and MEU aluminide fuels (2.2 gU/cm3) was performed. Thermal hydraulic study did not find any difficulty, however, neutronics study has some problems even when beryllium reflector is used instead of the existing graphite reflector. Namely, even when the LEU aluminide fuel is fully loaded in a whole fuel region, a goal depletion of 35 %U-235 can not be attained. On the other hand, the MEU aluminide fuel can get an upgraded performance. It is concluded that for continuation of the KUR operation, either one of the following fuels is needed: 1) the present HEU alloy fuel (0.5845 gU/cm3), 2) MEU aluminide fuel (<2.2 gU/cm3), or (3) LEU silicide fuel (3.2 gU/cm3). (Author)

Files

22069439.pdf

Files (143.2 kB)

Name Size Download all
md5:9fc1ff210a17c9ee9badcf3e9964d1e4
143.2 kB Preview Download

Additional details

Publishing Information

Publisher
CNEA.
Imprint Place
Buenos Aires (Argentina)
Imprint Title
Proceedings of the 10. International meeting on reduced enrichment research and test reactor [held in Buenos Aires, Argentina], September 28 - October 1, 1987
Imprint Pagination
501 p.
Journal Page Range
p. 303-310.
Report number
INIS-mf--12950

Conference

Title
10. international meeting on reduced enrichment research and test reactor.
Dates
28 Sep - 1 Oct 1987.
Place
Buenos Aires (Argentina).