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Title: Reactivity insertion transient analysis for KUR low-enriched uranium silicide fuel core
Authors: Shen, Xiuzhong  kyouindb  KAKEN_id  orcid (unconfirmed)
Nakajima, Ken  kyouindb  KAKEN_id  orcid (unconfirmed)
Unesaki, Hironobu  kyouindb  KAKEN_id
Mishima, Kaichiro
Author's alias: 沈, 秀中
Keywords: EUREKA-2/RR
Reactivity insertion transient analysis
Control rod withdrawal transient
Cold water injection transient
Irradiation samples removal transient
Issue Date: Dec-2013
Publisher: Elsevier Ltd.
Journal title: Annals of Nuclear Energy
Volume: 62
Start page: 195
End page: 207
Abstract: The purpose of this study is to realize the full core conversion from the use of High Enriched Uranium (HEU) fuels to the use of Low Enriched Uranium (LEU) fuels in Kyoto University Research Reactor (KUR). Although the conversion of nuclear energy sources is required to keep the safety margins and reactor reliability based on KUR HEU core, the uranium density (3.2 gU/cm3) and enrichment (20%) of LEU fuel (U3Si2–AL) are quite different from the uranium density (0.58 gU/cm3) and enrichment (93%) of HEU fuel (U–Al), which may result in the changes of heat transfer response and neutronic characteristic in the core. So it is necessary to objectively re-assess the feasibility of LEU silicide fuel core in KUR by using various numerical simulation codes. This paper established a detailed simulation model for the LEU silicide core and provided the safety analyses for the reactivity insertion transients in the core by using EUREKA-2/RR code. Although the EUREKA-2/RR code is a proven and trusted code, its validity was further confirmed by the comparison with the predictions from another two thermal hydraulic codes, COOLOD-N2 and THYDE-W at steady state operation. The steady state simulation also verified the feasibility of KUR to be operated at rated thermal power of 5 MW. In view of the core loading patterns, the operational conditions and characteristics of the reactor protection system in KUR, the accidental control rod withdrawal transients at natural circulation and forced circulation modes, the cold water injection induced reactivity insertion transient and the reactivity insertion transient due to removal of irradiation samples were conservatively analyzed and their transient characteristic parameters such as core power, fuel temperature, cladding temperature, primary coolant temperature and departure from nucleate boiling ratio (DNBR) due to the different ways and magnitudes of reactivity insertions were focused in this study. The analytical results indicate that the quick power excursions initiated by the reactivity insertion can be safely suppressed by the reactor protection system of KUR in various initial power levels and different operational modes (natural circulation and forced circulation modes). No boiling and no burnout on fuel cladding surface and no blister in the fuel meat happens and KUR is safe in all of these reactivity insertion transients if the reactor protection system of KUR works in its minimum degree.
Rights: © 2013 Elsevier Ltd.
This is not the published version. Please cite only the published version.
DOI(Published Version): 10.1016/j.anucene.2013.06.014
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