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JAEA Reports

Analytical study on creep behavior of a tube of coolant piping system in nuclear power plant (Contract research)

Miyazaki Noriyuki*; Hagiwara Seiya*; Chino, Eiichi*; Maruyama, Yu*; Hashimoto, Kazuichiro*; Maeda, Akio*

JAERI-Research 2001-047, 35 Pages, 2001/10

JAERI-Research-2001-047.pdf:1.63MB

no abstracts in English

Journal Articles

Effect of microstructure on failure behavior of light water reactor coolant piping under severe accident conditions

Harada, Yuhei; Maruyama, Yu; Maeda, Akio; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Hashimoto, Kazuichiro; Sugimoto, Jun

Journal of Nuclear Science and Technology, 36(10), p.923 - 933, 1999/10

 Times Cited Count:3 Percentile:28.69(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Metallurgical study of failed specimen and piping under LWR severe accident conditions

Harada, Yuhei; Maruyama, Yu; Maeda, Akio; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Hashimoto, Kazuichiro; Sugimoto, Jun

JAERI-Conf 99-005, p.171 - 175, 1999/07

no abstracts in English

Journal Articles

Experimental and analytical studies on creep failure of reactor coolant piping

Maeda, Akio; Maruyama, Yu; Hashimoto, Kazuichiro; Harada, Yuhei; Shibazaki, Hiroaki*; Kudo, Tamotsu; Nakamura, Naohiko; Hidaka, Akihide; Sugimoto, Jun

JAERI-Conf 99-005, p.165 - 170, 1999/07

no abstracts in English

Journal Articles

Creep analysis of piping with elevated internal pressure and temperature

Maeda, Akio; Maruyama, Yu; Hashimoto, Kazuichiro; Harada, Yuhei; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Sugimoto, Jun; Nakamura, Naohiko*

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

Journal Articles

Thermal and structural responses of reactor piping under elevated temperature and pressure conditions

Maeda, Akio; Maruyama, Yu; Nakamura, Naohiko*; Igarashi, Minoru*; Hashimoto, Kazuichiro*; Harada, Yuhei; Hidaka, Akihide; Sugimoto, Jun

Proc. of 5th Int. Conf. on Nuclear Engineering (ICONE-5), p.1 - 8, 1997/00

no abstracts in English

Journal Articles

Flow rate measurement and visualization in inclined pipe of helium-air exchange flow

Fumizawa, Motoo; Hishida, Makoto

Kashika Joho Gakkai-Shi, 15(SUPPL.2), p.169 - 172, 1995/10

no abstracts in English

Oral presentation

Analyses of pump/diagrid link rupture in pool type sodium-cooled fast reactor

Onoda, Yuichi; Uchita, Masato*; Tokizaki, Minako*; Okazaki, Hitoshi*

no journal, , 

The safety analyses were carried out to confirm the sufficiency of the function of the plant protection system against the pump/diagrid link rupture, which is a candidate of the design basis event in pool type SFR. Sensitivity has been studied for the parameters which are thought significantly to affect the detection of the pump/diagrid link rupture, such as initial reactor power (at rated and 30% power operation), reactivity feedbacks and so forth. The sufficiency of the function was confirmed by the analysis results that at least two signals are transmitted for the detection of the pump/diagrid link rupture, which is the development target of the plant protection system in pool type SFR.

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