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Journal Articles

Development of supercritical pressure water cooled solid breeder blanket in JAERI

Akiba, Masato; Ishitsuka, Etsuo; Enoeda, Mikio; Nishitani, Takeo; Konishi, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 79(9), p.929 - 934, 2003/09

no abstracts in English

Journal Articles

Air vent in water chamber and surface coating on liner slides concerning auxiliary cooling system for the high temperature engineering test reactor

Takeda, Takeshi; Kunitomi, Kazuhiko; ; *

Nucl. Eng. Des., 185(2-3), p.229 - 240, 1998/00

 Times Cited Count:12 Percentile:29.45(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of B$$_{4}$$C-carbon fiber composite ceramics as plasma facing materials in nuclear fusion reactor, 3; Heat resistance evaluation by electron beam irradiation and by in situ plasma discharge in JT-60

Jimbo, Ryutaro*; Saido, Masahiro; Nakamura, Kazuyuki; Akiba, Masato; ; Dairaku, Masayuki; *; *; *; *

Journal of the Ceramic Society of Japan, International Edition, 105, p.1179 - 1187, 1997/00

no abstracts in English

JAEA Reports

Journal Articles

Estimation of hot streak in core bottom structure of high temperature gas-cooled reactor; Thermal mixing test of coolant in core bottom structure of HENDEL

Inagaki, Yoshiyuki; Suzuki, Kunihiro; Ioka, Ikuo*; Kunitomi, Kazuhiko;

Nippon Kikai Gakkai Rombunshu, B, 57(542), p.3520 - 3525, 1991/10

no abstracts in English

JAEA Reports

Data report for ROSA-IV LSTF 10% hot leg break experiment Run SB-HL-04

Kukita, Yutaka; Nakamura, Hideo; *; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yonomoto, Taisuke; et al.

JAERI-M 91-040, 122 Pages, 1991/03

JAERI-M-91-040.pdf:3.42MB

no abstracts in English

JAEA Reports

Data report for ROSA-IV LSTF 10% hot leg break experiment; Run SB-HL-02

Kukita, Yutaka; *; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yamamoto, Nobuo; Nakamura, Hideo; et al.

JAERI-M 90-039, 122 Pages, 1990/03

JAERI-M-90-039.pdf:3.38MB

no abstracts in English

JAEA Reports

Data report for ROSA-IV/LSTF 5% hot leg break experiment Run SB-HL-01

Kukita, Yutaka; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yamamoto, Nobuo; Nakamura, Hideo; Yonomoto, Taisuke; et al.

JAERI-M 89-225, 117 Pages, 1990/01

JAERI-M-89-225.pdf:3.53MB

no abstracts in English

Journal Articles

Standard method of in-situ testing of HEPA filters in nuclear fuel facilities

Ikezawa, Yoshio; Matsui, Hiroshi; Yoshida, Yoshikazu*; *; *; *; *; *

Aerosols: Science,Industry,Health and Environment,Vol. 2, p.786 - 789, 1990/00

no abstracts in English

Journal Articles

Thermal performance test of the hot gas ducts of HENDEL

; ; ; Sanokawa, Konomo

Nucl.Eng.Des., 83, p.91 - 103, 1984/00

 Times Cited Count:4 Percentile:53.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Structure and performance of JAERI-type respiration fitting test apparatus

; ;

Hoken Butsuri, 13(4), p.301 - 305, 1978/00

no abstracts in English

JAEA Reports

Journal Articles

Leakage test of worn respirators by Sodium-chloride particles

; ;

Hoken Butsuri, 11(1), p.45 - 50, 1976/01

no abstracts in English

Oral presentation

Safety consideration for the introduction of new fuels and materials

Onizawa, Kunio

no journal, , 

After TEPCO Fukushima-Daiichi NPS accident, new fuels and materials have been developed in the OECD/NEA member countries. The objective of the development is to have new fuels with enhanced accident tolerance, especially for severe accident conditions. For the new fuel development, similar to the conventional ones, many kinds of information are necessary to maintain the safety functions of the fuel. The fuel safety should be confirmed not only for severe accidents, but also for various conditions such as normal operation, design basis accidents, transportation and so on. Preparation of experimental databases with high reliability and analytical tools are also needed to confirm the safety of the new fuels. Therefore, test reactors and hot laboratories play important roles in the acquisition of in-reactor data which are the key information as the technical basis of safety judgement. In this presentation, safety requirements under various plant conditions which are considered in the new fuel development is explained. The importance of experiments using test reactors and laboratories for new fuel development is also explained including examples of JAEA facilities.

18 (Records 1-18 displayed on this page)
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