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JAEA Reports

Research report on information of the Nuclear Ship "MUTSU" (Contract research)

Aomori Research and Development Center

JAEA-Review 2022-039, 36 Pages, 2023/02

JAEA-Review-2022-039.pdf:4.3MB

In order to use for the consideration of floating nuclear power plant, results of survey about actual process and literature are summarized in this report.

JAEA Reports

Consideration on roles and relationship between observations/measurements and model predictions for environmental consequence assessments for nuclear facilities

Togawa, Orihiko; Okura, Takehisa; Kimura, Masanori

JAEA-Review 2022-049, 76 Pages, 2023/01

JAEA-Review-2022-049.pdf:3.74MB

Before construction and after operation of nuclear facilities, environmental consequence assessments are conducted for normal operation and an emergency. These assessments mainly aim at confirming safety for the public around the facilities and producing relief for them. Environmental consequence assessments are carried out using observations/ measurements by environmental monitoring and/or model predictions by calculation models, sometimes using either of which and at other times using both them, according to the situations and necessities. First, this report investigates methods, roles, merits/demerits and relationship between observations/measurements and model predictions which are used for environmental consequence assessments of nuclear facilities, especially holding up a spent nuclear fuel reprocessing plant at Rokkasho, Aomori as an example. Next, it explains representative examples of utilization of data on observations/measurements and results on model predictions, and considers points of attention at using them. Finally, the report describes future direction, for example, improvements of observations/measurements and model predictions, and fusion of both them.

Journal Articles

Simulation of a marine nuclear reactor

Kusunoki, Tsuyoshi; Kyoya, Masahiko; ;

Nuclear Technology, 109, p.275 - 285, 1995/02

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Performance evaluation of nuclear ship engineering simulation system

Kyoya, Masahiko; ; Kusunoki, Tsuyoshi; ; Takahashi, Teruo*

JAERI-M 94-079, 116 Pages, 1994/06

JAERI-M-94-079.pdf:3.19MB

no abstracts in English

Journal Articles

Shielding design of obtain compact marine reactor

;

Journal of Nuclear Science and Technology, 31(6), p.510 - 520, 1994/06

 Times Cited Count:16 Percentile:78.26(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of Nuclear Ship Engineering Simulation System, NESSY

Kusunoki, Tsuyoshi; Kyoya, Masahiko; Takahashi, Teruo*; ; ;

JAERI-M 93-223, 176 Pages, 1993/11

JAERI-M-93-223.pdf:4.18MB

no abstracts in English

Journal Articles

Comparison between measured and design dose rate equivalents on board of nuclear ship Mutsu

; Sakamoto, Yukio

Journal of Nuclear Science and Technology, 30(9), p.926 - 945, 1993/09

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Journal Articles

Development of simplified computer codes for impact analysis of radioactive materials transport casks, 1st report; Computer code CRUSH for impact analysis of casks with shock absorbers

;

Nihon Genshiryoku Gakkai-Shi, 33(4), p.381 - 390, 1991/04

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of ex-core detector response measured during nuclear ship Mutsu land-loaded core critical experiment

; ;

Nuclear Technology, 78(8), p.140 - 150, 1987/08

no abstracts in English

Journal Articles

Benchmark study of some thermal and structural computer codes for nuclear shipping casks

; Nanae, Y.*; Shimada, H.*; Shimada, A.*

Nihon Genshiryoku Gakkai-Shi, 26(9), p.781 - 792, 1984/00

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Mockup experiments for the irregular shield of the first nuclear ship of Japan

; ; H.YAMAKI*; Y.TOYODA*; Y.NAKANO*; T.FUSE*; T.MIURA*

Nucl.Eng.Des., 7(2), p.152 - 158, 1968/00

 Times Cited Count:0

no abstracts in English

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