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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.

JAEA Reports

Operation, test, research and development of the High Temperature Engineering Test Reactor (HTTR) (FY2017)

Department of HTTR

JAEA-Review 2019-006, 97 Pages, 2019/07

JAEA-Review-2019-006.pdf:10.18MB

The High Temperature Engineering Test Reactor (HTTR) was constructed to establish and upgrade basic technologies for HTGRs. In the fiscal year 2017 we continued activities for re-operation of the HTTR and have been inspected the application document for the HTTR licensing to prove conformity with the new regulatory requirements for research reactors taken effect since December 2013 had been applied. This report summarizes activities and results of HTTR operation, maintenance, international cooperation and so on which were carried out in the fiscal year 2017.

JAEA Reports

Study on temperature coefficients of reactivity for pebble bed type HTGRs loaded with highly $$^{239}$$Pu-enriched plutonium

; Yamashita, Kiyonobu; Shindo, Ryuichi; Fujimoto, Nozomu

JAERI-Tech 96-025, 50 Pages, 1996/06

JAERI-Tech-96-025.pdf:1.3MB

no abstracts in English

Journal Articles

Upgrading of block type HTGRs' core with axial fuel shuffling

Yamashita, Kiyonobu

Nihon Genshiryoku Gakkai-Shi, 37(3), p.213 - 216, 1995/00

 Times Cited Count:0 Percentile:0.54(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Seismic study on high temperature gas-cooled reactor core

JAERI 1322, 157 Pages, 1991/04

JAERI-1322.pdf:5.34MB

no abstracts in English

Journal Articles

Seismic response of high temperature gas-cooled reactor core with block-type fuel, IV; Seismic reaponse of actual core predicted from experimental and analytical results of two-dimensional core modela

;

Nihon Genshiryoku Gakkai-Shi, 27(2), p.145 - 158, 1985/00

 Times Cited Count:2 Percentile:37.44(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Seismic response of high temperature gas-cooled reactor core with block-type fuel,III; Vibration experiment of two-dimensional vertical slice core model

;

Journal of Nuclear Science and Technology, 18(7), p.514 - 524, 1981/00

 Times Cited Count:3 Percentile:45.64(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Journal Articles

A Seismic analysis method for a block column gas-cooled reactor core

;

Nucl.Eng.Des., 55(3), p.331 - 342, 1979/00

 Times Cited Count:16

no abstracts in English

Journal Articles

Contact visco-elastic stress analysis using F.E.M.

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Nihon Genshiryoku Gakkai-Shi, 19(11), p.774 - 781, 1977/11

 Times Cited Count:0

no abstracts in English

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