Transient Behavior of Low Enriched Uranium Silicide Plate-Type Fuel for Research Reactors during Reactivity Initiated Accident Conditions.
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概要
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This paper describes the results of transient experiments using a low enriched uranium silicide miniplate fuel for research reactor. The pulse irradiation was performed in the Nuclear Safety Research Reactor (NSRR) at the Japan Atomic Energy Research Institute (JAERI). <BR>The results obtained in this study are summarized as follows :<BR>(1) The tested fuel plates were damaged with energy depositions above 94 cal/g-fuel, but remained intact below 82 cal/g-fuel. A failure threshold should therefore exist between these two values.<BR>(2) Four of the fuel plates that showed peak cladding surface temperatures <330°C were damaged by the thermal stress during quenching. These damaged fuel plates revealed small intergranular cracks that propagated perpendicularly to the axial direction of the plate, from the Al cladding surface to the fuel core, without significant dimensional changes. On the other hand, when peak cladding surface temperatures were >400°C, the test fuel plates were damaged mainly by melting of the Al cladding, accompanying significant dimensional changes.<BR>(3) The thermal stress of the damaged fuel plates calculated on the basis of the maximum transient temperature drop during quenching was greater than the tensile stress that occurred during fabrication.
- 一般社団法人 日本原子力学会の論文
著者
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Yanagisawa Kazuaki
Japan Atomic Energy Agency
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FUJISHIRO Toshio
Japan Atomic Energy Research Institute
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Yanagisawa Kazuaki
Japan Atomic Energy Research Institute
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Soyama Kazuhiko
Japan Atomic Energy Research Institute
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KODAIRA Tsuneo
Japan Atomic Energy Research Institute
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HORIKI Oichiro
Japan Atomic Energy Research Institute
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ICHIKAWA Hiroki
Japan Atomic Energy Research Institute
関連論文
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- Transient Behavior of Low Enriched Uranium Silicide and Aluminide Miniplate Fuel for Research Reactors
- Transient Behavior of Low Enriched Uranium Silicide Miniplate Fuel under a Triplet Configuration
- Pellet-Cladding Mechanical Interaction of PWR Fuel Rod Under Rapid Power Transient
- Out-of-Pile Anneal Experiment of PWR Fuel at Burn-Up of 39 MWd/kg U
- Transient Behavior of Waterside Corroded PWR Fuel
- Transient Behavior of Low Enriched Uranium Silicide Plate-Type Fuel for Research Reactors during Reactivity Initiated Accident Conditions.
- Irradiation studies of JAERI's fuel at Halden Reactor.
- In-pile eddy current test on PWR fuel rod failed by pellet-cladding interaction.