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JAEA Reports

Behavior of irradiated PWR fuel under simulated RIA conditions; Results of the NSRR tests GK-1 and GK-2

Sasajima, Hideo; Sugiyama, Tomoyuki; Nakamura, Takehiko*; Fuketa, Toyoshi

JAERI-Research 2004-022, 113 Pages, 2004/12

JAERI-Research-2004-022.pdf:47.48MB

Results from power burst tests, GK-1 and GK-2, conducted at the NSRR, are summarized. The tests were performed on a 14$$times$$14 PWR fuel rod irradiated to a burnup of 42 MWd/kgU in the Genkai unit #1 of Kyushu Electric Power Co., Inc. The instrumented test fuel rod in a double-container-type capsule was subjected to the pulse-irradiation with stagnant water cooling condition at 0.1 MPa and 293 K. Deposited energy and peak fuel enthalpy were 505 J/g and 389 J/g in the Test GK-1, and 490 J/g and 377 J/g in the Test GK-2, respectively. During the pulse-irradiations, DNB occurred and the cladding surface temperature reached 581 K and 569 K in the Tests GK-1 and -2, respectively. The maximum cladding hoop strain was 2.7% in the Test GK-1 and 1.2% in the Test GK-2. However, the test fuel rods did not fail. Estimated fission gas releases during the pulse-irradiations were 11.7% and 7.0% in the Tests GK-1 and -2, respectively.

Journal Articles

Fission gas release behavior of high burnup UO$$_{2}$$ fuel under reactivity initiated accident conditions

Sasajima, Hideo; Nakamura, Jinichi; Fuketa, Toyoshi; Uetsuka, Hiroshi

Journal of Nuclear Science and Technology, 36(11), p.1101 - 1104, 1999/11

 Times Cited Count:2 Percentile:21.18(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Interaction of molten aluminum cladding with U$$_{3}$$Si$$_{2}$$ particles under transient conditions

Yanagisawa, Kazuaki

JAERI-M 93-129, 18 Pages, 1993/07

JAERI-M-93-129.pdf:1.09MB

no abstracts in English

Journal Articles

Studies of transient behavior of low enriched silicide fuel plates by pulse-irradiation in the NSRR

Yanagisawa, Kazuaki; ; ; Horiki, Oichiro; Soyama, Kazuhiko; Ichikawa, Hiroki; Kodaira, Tsuneo; Yamahara, Takeshi

Proc. of the 3rd Asian Symp. on Research Reactor, p.391 - 398, 1991/00

no abstracts in English

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