TRANSIENT-BEHAVIOR OF LOW ENRICHED URANIUM SILICIDE AND ALUMINIDE MINIPLATE FUEL FOR RESEARCH REACTORS

Citation
K. Yanagisawa et T. Fujishiro, TRANSIENT-BEHAVIOR OF LOW ENRICHED URANIUM SILICIDE AND ALUMINIDE MINIPLATE FUEL FOR RESEARCH REACTORS, Journal of Nuclear Science and Technology, 32(9), 1995, pp. 889-897
Citations number
8
Categorie Soggetti
Nuclear Sciences & Tecnology
ISSN journal
00223131
Volume
32
Issue
9
Year of publication
1995
Pages
889 - 897
Database
ISI
SICI code
0022-3131(1995)32:9<889:TOLEUS>2.0.ZU;2-G
Abstract
This paper describes the results of transient experiments using a low enriched uranium silicide (density, 4.0 g U/cm(3)) and aluminide (dens ity, 2.2 g U/cm(3)) miniplate fuels prepared for the Japan Research Re actor-3 (JRR-3). The transient irradiation was performed in the Nuclea r Safety Research Reactor (NSRR) at the Japan Atomic Energy Research I nstitute (JAERI). The results obtained are summarized below. (1) The t ested silicide miniplate fuel, which will be a candidate for a future low enriched fuel in the JRR-3 core, did not fail with an energy depos ition of 106 cal/g . fuel at a peak cladding surface temperature (PCST ) of 508 degrees C. This condition simulated a transient causing blist er failure, which was assumed to occur above the PCST of 400 degrees C . Accordingly, the tested silicide miniplate fuel had a strong resista nce against blistering up to 508 degrees C. (2) The tested aluminide m iniplate fuel did not fail with an energy deposition of 55 cal/g . fue l at a PCST of 230 degrees C. This condition simulated an accidental m ater channel closure, which was assumed in the safety analysis of JRR- 3. The predicted PCST by using the EUREKA-2 code was about 150 degrees C. Accordingly the conventional aluminide fuel used in JRR-3 was foun d to be intact under a simulated mater channel closure accident.