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JAEA Reports

Study on system layout and component design in the HTTR hydrogen production system (Contract research)

Nishihara, Tetsuo; Shimizu, Akira; Tanihira, Masanori*; Uchida, Shoji*

JAERI-Tech 2002-101, 46 Pages, 2003/01

JAERI-Tech-2002-101.pdf:2.6MB

no abstracts in English

JAEA Reports

Conceptual design of the handling and storage system of the spent target vessel for neutron scattering facility, 2

Adachi, Junichi*; Kaminaga, Masanori; Sasaki, Shinobu; Haga, Katsuhiro; Aso, Tomokazu; Kinoshita, Hidetaka; Hino, Ryutaro

JAERI-Tech 2001-093, 108 Pages, 2002/01

JAERI-Tech-2001-093.pdf:7.49MB

In designing of the neutron scattering facility, a spent target vessel should be replaced with remote handling devices in order to protect radioactive exposure, since it would be highly. In the storage of the spent target vessel, it is necessary to consider decay heat of the target vessel and mercury contamination caused by vaporization of the residual mercury in the vessel. A conceptual design has been carried out to establish basic concept and to clarify its specification of main equipments on a handling and storage system for the spent target vessel. This report presents the basic concept and a system plot plan based on latest design works of remote handling devices, which aim at reasonability and simplification.

JAEA Reports

Conceptual design of solid breeder blanket system cooled by supercritical water

Enoeda, Mikio; Ohara, Yoshihiro; Akiba, Masato; Sato, Satoshi; Hatano, Toshihisa; Kosaku, Yasuo; Kuroda, Toshimasa*; Kikuchi, Shigeto*; Yanagi, Yoshihiko*; Konishi, Satoshi; et al.

JAERI-Tech 2001-078, 120 Pages, 2001/12

JAERI-Tech-2001-078.pdf:8.3MB

This report is a summary of the design works, which was discussed in the design workshop held in 2000 for the demonstration (DEMO) blanket aimed to strengthen the commercial competitiveness and technical feasibility simultaneously. The DEMO blanket must supply the feasibility and experience of the total design of the power plant and the materials. This conceptual design study was performed to determine the updated strategy and goal of the R&D of the DEMO blanket which applies the supercritical water cooling proposed in A-SSTR, taking into account the recent progress of the plasma research and reactor engineering technology.

JAEA Reports

Proposal of safety design methodologies for an HTGR-hydrogen production system; Mainly on countermeasures against fire and explosion

Nishihara, Tetsuo; Hada, Kazuhiko; Shiozawa, Shusaku

JAERI-Research 97-022, 110 Pages, 1997/03

JAERI-Research-97-022.pdf:4.1MB

no abstracts in English

Journal Articles

Advantage of modified JAERI passive safety reactor (JPSR-II)

Murao, Yoshio; Ochiai, Masaaki

Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 2, p.1075 - 1085, 1997/00

no abstracts in English

Journal Articles

Conceptual design study of accelerator-driven systems for nuclear waste transmutation

Takizuka, Takakazu; ; Sasa, Toshinobu

Proc. of 2nd Int. Conf. on Accelerator-Driven Transmutation Technologies and Applications, 1, p.179 - 185, 1996/06

no abstracts in English

Journal Articles

Universally applicable design concept of stably controlling an HTGR-hydrogen production system

Hada, Kazuhiko; Shibata, Taiju; Nishihara, Tetsuo; Shiozawa, Shusaku

Nihon Genshiryoku Gakkai-Shi, 38(10), p.834 - 844, 1996/00

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

no abstracts in English

Journal Articles

Nuclear waste transmutation by accelerator-based system

Takizuka, Takakazu

21-seiki Ni Muketa Genshi Nenryo Saikuru No Kadaito Tembo, p.127 - 150, 1994/03

no abstracts in English

JAEA Reports

Development of Tokamak Reactor Systems Analysis Code "TORSAC"

; Tone, Tatsuzo; *; *

JAERI-M 87-021, 272 Pages, 1987/02

JAERI-M-87-021.pdf:4.66MB

no abstracts in English

Journal Articles

Design concept and experience of a system for prediction of environmental emergency dose information (SPEEDI).

; ; ; ; ; ;

Nihon Genshiryoku Gakkai-Shi, 27(9), p.839 - 850, 1985/00

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

no abstracts in English

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