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Journal Articles

Derivation of ideal power distribution to minimize the maximum kernel migration rate for nuclear design of pin-in-block type HTGR

Okita, Shoichiro; Fukaya, Yuji; Goto, Minoru

Journal of Nuclear Science and Technology, 58(1), p.9 - 16, 2021/01

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Suppressing the kernel migration rates, which depend on both the fuel temperature and the fuel temperature gradient, under normal operation condition is quite important from the viewpoint of the fuel integrity for High Temperature Gas-cooled Reactors. The presence of the ideal axial power distribution to minimize the maximum kernel migration rate allows us to improve efficiency of design work. Therefore, we propose a new method based on Lagrange multiplier method in consideration of thermohydraulic design in order to obtain the ideal axial power distribution to minimize the maximum kernel migration rate. For one of the existing conceptual designs performed by JAEA, the maximum kernel migration rate for the power distribution to minimize the maximum kernel migration rate proposed in this study is lower by approximately 10% than that for the power distribution as a conventional design target to minimize the maximum fuel temperature.

Journal Articles

Coated fuel particle; Small particles for nuclear fuel

Minato, Kazuo

Zusetsu Zoryu; Tsubu No Sekai Arekore, p.131 - 133, 2001/10

no abstracts in English

JAEA Reports

Preirradiation characterization of HTGR fuel for HRB-22 capsule irradiation test; JAERI/USDOE collaborative irradiation test for HTGR fuel

Minato, Kazuo; ; Sawa, Kazuhiro; Tobita, Tsutomu; Fukuda, Kosaku

JAERI-Tech 95-056, 45 Pages, 1996/01

JAERI-Tech-95-056.pdf:3.02MB

no abstracts in English

JAEA Reports

Evaluation of coated fuel particle temperature during reactivity insertion events

Sawa, Kazuhiro; Nakagawa, Shigeaki; Minato, Kazuo; Shiozawa, Shusaku

JAERI-M 92-175, 34 Pages, 1992/11

JAERI-M-92-175.pdf:0.62MB

no abstracts in English

JAEA Reports

Assessment of fuel integrity of the High Temperature Engineering Test Reactor(HTTR) and its permissible design limit

Hayashi, Kimio; Sawa, Kazuhiro; Shiozawa, Shusaku; Fukuda, Kosaku

JAERI-M 89-162, 83 Pages, 1989/10

JAERI-M-89-162.pdf:2.53MB

no abstracts in English

Journal Articles

Crushing strength of fuel kernels for high-temperature gas-cooled reactors

Akabori, Mitsuo; Shiba, Koreyuki

Journal of Nuclear Science and Technology, 21(6), p.466 - 475, 1984/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Electron Probe Micro-Analysis of Irradiated Triso-Coated UO$$_{2}$$ Particles, I

; Minato, Kazuo; ; Ikawa, Katsuichi

JAERI-M 83-200, 34 Pages, 1983/11

JAERI-M-83-200.pdf:1.37MB

no abstracts in English

JAEA Reports

Sol Production Apparatus of pH Control Type

; ; Shiba, Koreyuki

JAERI-M 9477, 26 Pages, 1981/05

JAERI-M-9477.pdf:1.05MB

no abstracts in English

JAEA Reports

Studies on irradiation behaviors of coated particle fuels

; Iwamoto, K.; Ikawa, Katsuichi

JAERI-M 9071, 50 Pages, 1980/08

JAERI-M-9071.pdf:1.91MB

no abstracts in English

Journal Articles

Computer codes for ractor physis analysis

Genshiryoku Kogyo, 21(6), p.70 - 74, 1975/06

no abstracts in English

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