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JAEA Reports

Development of fuel temperature calculation file for high temperature gas-cooled reactors

Inaba, Yoshitomo; Isaka, Kazuyoshi; Fukaya, Yuji; Tachibana, Yukio

JAEA-Data/Code 2014-023, 64 Pages, 2015/01

JAEA-Data-Code-2014-023.pdf:7.15MB

The Japan Atomic Energy Agency has performed the conceptual designs of small-sized High Temperature Gas-cooled Reactor (HTGR) systems, aiming for the deployment of the systems to overseas such as developing countries. The small-sized HTGR systems can provide power generation by steam turbine, high temperature steam for industry process and/or low temperature steam for district heating. In the core thermal and hydraulic designs of HTGRs, it is important to evaluate the maximum fuel temperature so that the thermal integrity of the fuel is ensured. In order to calculate and evaluate the fuel temperature on personal computers (PCs) in a convenient manner, the calculation file based on the Microsoft Excel were developed. In this report, the basic equations used in the calculation file, the calculation method and procedure, and the results of the validation calculation are described.

Journal Articles

Design study around beam window of ADS

Oigawa, Hiroyuki; Tsujimoto, Kazufumi; Kikuchi, Kenji; Kurata, Yuji; Sasa, Toshinobu; Umeno, Makoto*; Nishihara, Kenji; Saito, Shigeru; Mizumoto, Motoharu; Takano, Hideki*; et al.

Proceedings of 4th International Workshop on the Utilisation and Reliability of High Power Proton Accelerators, p.325 - 334, 2005/11

The Japan Atomic Energy Research Institute (JAERI) is conducting the research and development (R&D) on the Accelerator-Driven Subcritical System (ADS) for the effective transmutation of minor actinides (MAs). The ADS proposed by JAERI is the 800 MWth, Pb-Bi cooled, tank-type subcritical reactor loaded with (MA+Pu) nitride fuel. The Pb-Bi is also used as the spallation target. In this study, the feasibility of the ADS was discussed with putting the focus on the design around the beam window. The partition wall was placed between the target region and the ductless-type fuel assemblies to keep the good cooling performance for the hot-spot fuel pin. The flow control nozzle was installed to cool the beam window effectively. The thermal-hydraulic analysis showed that the maximum temperature at the outer surface of the beam window could be repressed below 500 $$^{circ}$$C even in the case of the maximum beam power of 30 MW. The stress caused by the external pressure and the temperature distribution of the beam window was also below the allowable limit.

Journal Articles

Nuclear, thermal and hydraulic design for Gas Turbine High Temperature Reactor (GTHTR300)

Nakata, Tetsuo*; Katanishi, Shoji; Takada, Shoji; Yan, X.; Kunitomi, Kazuhiko

Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.478 - 489, 2003/12

no abstracts in English

JAEA Reports

Multi-dimensional design window search system using neural networks in reactor core design

Kugo, Teruhiko; Nakakawa, Masayuki

JAERI-Data/Code 2000-004, p.97 - 0, 2000/02

JAERI-Data-Code-2000-004.pdf:10.51MB

no abstracts in English

Journal Articles

Experimental study on the critical heat flux (CHF) in a rectangular channel with micro ribs for a solid target and proton beam window design

Kaminaga, Masanori; Kinoshita, Hidetaka; Haga, Katsuhiro; Hino, Ryutaro; Sudo, Yukio

Proceedings of International Workshop on Current Status and Future Directions in Boiling Heat Transfer and Two-Phase Flow, p.135 - 141, 2000/00

no abstracts in English

Journal Articles

Application of neural network to multi-dimensional design window search in reactor core design

Kugo, Teruhiko; Nakakawa, Masayuki

Journal of Nuclear Science and Technology, 36(4), p.332 - 343, 1999/04

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

no abstracts in English

Journal Articles

Development of intelligent code system to support conceptual design of nuclear reactor core

Kugo, Teruhiko; Nakakawa, Masayuki;

Journal of Nuclear Science and Technology, 34(8), p.760 - 770, 1997/08

 Times Cited Count:2 Percentile:23.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of core thermal-hydraulics module for intelligent reactor design system (IRDS)

Kugo, Teruhiko; Fujii, Sadao*; Nakakawa, Masayuki

JAERI-Data/Code 94-001, 187 Pages, 1994/08

JAERI-Data-Code-94-001.pdf:7.51MB

no abstracts in English

Journal Articles

Evaluation of hot spot factors for thermal and hydraulic design of HTTR

Maruyama, So; Yamashita, Kiyonobu; Fujimoto, Nozomu; Murata, Isao; Sudo, Yukio; Murakami, Tomoyuki*; Fujii, Sadao*

Journal of Nuclear Science and Technology, 30(11), p.1186 - 1194, 1993/11

 Times Cited Count:7 Percentile:68.63(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Entry-length effect on the thermal-hydraulic design of plasma-facing components of fusion reactors, Part I; Non-MHD flow

Kunugi, Tomoaki; M.Z.Hasan*

Fusion Technology, 19, p.1024 - 1029, 1991/05

no abstracts in English

Journal Articles

Entry-length effect on the thermal-hydraulic design of plasma-facing components of fusion reactors, Part II; MHD flow

M.Z.Hasan*; Kunugi, Tomoaki

Fusion Technology, 19, p.1030 - 1035, 1991/05

no abstracts in English

Journal Articles

Thermal and hydraulic design for High Temperature Engineering Test Reactor(HTTR)

Maruyama, So; Yamashita, Kiyonobu; Fujimoto, Nozomu; Murata, Isao; Shindo, Ryuichi; Sudo, Yukio

The Safety,Status and Future of Non-Commercial Reactors and Irradiation Facilities,Vol. 1, p.304 - 311, 1990/09

no abstracts in English

JAEA Reports

Core Hydrodynamic Tests and Determination of Core Flow of JRR-3 to Be Renewed ata 20MWt

Sudo, Yukio; ; *;

JAERI-M 84-119, 108 Pages, 1984/06

JAERI-M-84-119.pdf:2.16MB

no abstracts in English

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