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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.

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

Conceptual design of a 50-MW severe-accident-free HTR and the related test program of the HTTR

Kunitomi, Kazuhiko; Tachibana, Yukio; Saikusa, Akio; Sawa, Kazuhiro; L.M.Lidsky*

Nuclear Technology, 123(3), p.245 - 258, 1998/09

 Times Cited Count:4 Percentile:39.76(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:23.97(Nuclear Science & Technology)

no abstracts in English

Journal Articles

JPSR (JAERI Passive Safety Reactor)

Murao, Yoshio

Nihon Genshiryoku Gakkai-Shi, 37(9), p.784 - 787, 1995/00

no abstracts in English

Journal Articles

Concept of passive safety light water reactor system (JPSR)

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Enginering (ICONE), Vol. 2, 0, p.723 - 728, 1995/00

no abstracts in English

Journal Articles

Conceptual design of the JAERI passive safety reactor and its thermal-hydraulic characteristics

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke

Transactions of the American Nuclear Society, 71, p.527 - 529, 1995/00

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

Conceptual design of JAERI passive safety reactor (JPSR) and its thermal-hydraulic characteristics

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke

10th Proc. of Nuclear Thermal Hydraulics, 0, p.3 - 12, 1994/00

no abstracts in English

Journal Articles

Design window search based on AI technique

Nakakawa, Masayuki; Fujii, Sadao*; *; *

Journal of Nuclear Science and Technology, 29(11), p.1116 - 1119, 1992/11

no abstracts in English

JAEA Reports

Development of a BWR core burn-up calculation code COREBN-BWR

*; Okumura, Keisuke

JAERI-M 92-068, 107 Pages, 1992/05

JAERI-M-92-068.pdf:2.79MB

no abstracts in English

13 (Records 1-13 displayed on this page)
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