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Journal Articles

Prospects based on T-H roadmap through communication

Nakamura, Hideo

Nippon Genshiryoku Gakkai-Shi, 61(4), p.270 - 272, 2019/04

no abstracts in English

Journal Articles

Let's aim at AESJ without Ethics Committee

Oba, Kyoko

Nippon Genshiryoku Gakkai-Shi, 61(4), p.347 - 348, 2019/04

This article is published in a special feature in commemoration of the 60th anniversary of the Atomic Energy Society of Japan. The article is the contents that "I look back on this, and surveys the future", by chairwoman of Ethics Committee.

Journal Articles

Issues associated with radiation protection after Fukushima Daiichi Nuclear Power Plant disaster

Yamasoto, Kotaro

Gijutsushi, 27(11), p.8 - 11, 2015/11

Various analysis reports focused on Fukushima Daiichi Nuclear Power Plant disaster have been published from government, national diet, private group and Tokyo electric power company. Japan Health Physics Society (JHPS) analyzed these reports on perspective of radiation protection, and has reported towards the national and international society as "second-order recommendation report". What are radiation protection issues that have been found from these analysis reports? What is the direction of the goal of radiation protection system at the time of nuclear accident? From the results of these analyzes, many challenges have been found in current nuclear disaster prevention system.

Journal Articles

INMM 44th Annual Meeting, 3; Environmental sample analysis for safeguards

Usuda, Shigekazu

Kaku Busshitsu Kanri Senta Nyusu, 32(10), p.5 - 6, 2003/10

no abstracts in English

Journal Articles

Aiming at further improvement of prediction for consequences of LWR severe accidents

Hidaka, Akihide

Nippon Genshiryoku Gakkai-Shi, 45(8), p.493 - 496, 2003/08

In order to investigate the radionuclides release from irradiated fuel under severe accident conditions of LWR, VEGA experimental facility that realizes the highest temperature and pressure conditions was designed and constructed at JAERI. The effect of ambient pressure on radionuclides release was uniquely quantified by using this facility. A model that explains the observed pressure effect was also proposed based on the experimental results. For this effort, the atomic energy society of Japan gave us the preeminent monograph award in FY 2002. This paper describes my encounter with the research awarded this time, fascination of this research, hard-worked points, future plans and so on.

Journal Articles

Letter from Division of Nuclear Fuel Cycle and Environment, Atomic Energy Society of Japan

Sakamoto, Yoshiaki

Nippon Genshiryoku Gakkai-Shi, 45(2), P. 141, 2003/02

no abstracts in English

Journal Articles

Report on the 6th International Conference on Tritium Science and Technology

Nishi, Masataka; Yamanishi, Toshihiko

Nippon Genshiryoku Gakkai-Shi, 44(6), p.488 - 489, 2002/06

no abstracts in English

Journal Articles

Report on 43rd APS Meeting

Kubo, Hirotaka; Sugama, Hideo*; Murakami, Masakatsu*; Osawa, Yukiharu*

Purazuma, Kaku Yugo Gakkai-Shi, 77(12), p.1252 - 1253, 2001/12

no abstracts in English

Journal Articles

On Hanichi Muraoka

Uehara, Kazuya

Daigaku No Butsuri Kyoiku, 3, p.9 - 13, 2000/11

no abstracts in English

Journal Articles

Report of Monte Carlo calculation summer seminar

Sakurai, Kiyoshi; Kume, Etsuo; Yatabe, Shigeru*; Maekawa, Fujio; Yamamoto, Toshihiro; Nagaya, Yasunobu; Mori, Takamasa; Ueki, Kotaro*; Naito, Yoshitaka*

Nippon Genshiryoku Gakkai-Shi, 42(10), p.1062 - 1065, 2000/10

no abstracts in English

JAEA Reports

Experimental study on the avoidance and suppression criteria for the vortex-induced vibration of a circular cylinder

; ; ;

JNC-TN9400 2000-012, 43 Pages, 2000/03

JNC-TN9400-2000-012.pdf:2.12MB

Experimental validation of the design method to prevent the failure of a thermometer well by the vortex-induced vibration has been performed for the effect of structure damping of a cylinder. The available experimental data in piping were very limited for the high damping region in water flow, because of the difficulty to increase the structure dumping for the one-side supported cylinder in experiments. ln this experiment, high viscosity fluid was charged into the tested cylinders to control the cylinder's damping. Resulting values of the reduced damping are 0.49, 0.96, 1.23, 1.98, 2.22 in the experiments. Reduced velocity(Vr) was increased gradually in the range of 0.7 $$leq$$ Vr $$leq$$ 5(Reynolds number at Vr=1 is 8$$times$$10$$^{4}$$). The displacements of the cylinder by the vortex-induced vibration were measured. As the results, Tested cylinders of reduced damping 0.49 and 0.96 showed vortex-induced vibration in flow direction at Vr $$>$$ 1 region. However, in case of reduced damping of 1.23, 1.98 and 2.22, the vortex-induced vibrations in flow direction were suppressed lower than the 1% displacement of the cylinder diameter. ln conclusion, it is confirmed that the suppression criteria of the "Vr $$<$$ 3.3 and Cn $$>$$ 1.2" for vortex-induced vibration in flow direction, which is used in ASME code; "Boiler and Pressure VesseI Code Sec.III Appendix N-1300" and the "FIV design guide in JNC", is reasonably applicable to the one-side supported cylinder in water flow piping.

Journal Articles

Overview of recent research activities of Monte Carlo simulation in Japan

Sakurai, Kiyoshi; Yamamoto, Toshihiro; Ueki, Kotaro*; Mori, Takamasa; Nomura, Yasushi; Naito, Yoshitaka*

Journal of Nuclear Science and Technology, 37(Suppl.1), p.446 - 448, 2000/03

no abstracts in English

JAEA Reports

Low temperature creep and stress corrosion cracking tests of rupture disk (Alloy600)

; *; Yoshida, Eiichi; Aoto, Kazumi

JNC-TN9400 2000-011, 33 Pages, 1999/03

JNC-TN9400-2000-011.pdf:13.45MB

The damage was observed in rupture disk for the A-loop superheater of sodium-water reaction products releasing system for MONJU on March 3, 1998. Low temperature creep and stress corrosion cracking tests were carried out as the causes investigation of the damage. As the result, the followings are clarified. (1)The possibility that low temperature creep is the principal damage is small. (2)The stress corrosion cracking under NaOH environment due to the reaction of Na vapor and moisture condensed on the surface of glass beads as remains is the most probable cause on the damage. (3)Comparatively many glass beads remained in damaged surface. The gap between rupture disk and vacuum support was narrower than other parts, and they were not directly exposed to the Na vapor for a long time. The above factors caused the perfect intergranular cracking by stress corrosion. Since NaOH was chemically changed into the harmless Na$$_{2}$$O on the location except for damaged zone by full Na vapor, the stress corrosion cracking was not generated.

JAEA Reports

None

PNC-TJ1309 98-001, 161 Pages, 1998/02

PNC-TJ1309-98-001.pdf:5.01MB

no abstracts in English

JAEA Reports

None

PNC-TJ1309 97-001, 112 Pages, 1997/03

PNC-TJ1309-97-001.pdf:3.5MB

no abstracts in English

Journal Articles

Report on the 37th Annual Meeting of the Division of Plasma Physics of the American Physical Society

Kimura, Haruyuki

Purazuma, Kaku Yugo Gakkai-Shi, 72(2), p.170 - 171, 1996/02

no abstracts in English

Journal Articles

Closing report on the research committee of nuclear transmutation

Mukaiyama, Takehiko

Nippon Genshiryoku Gakkai-Shi, 37(5), 469 Pages, 1995/00

no abstracts in English

JAEA Reports

None

; Sumiya, Shuichi;

PNC-TN8450 94-006, 28 Pages, 1994/12

no abstracts in English

JAEA Reports

None

;

PNC-TN8600 92-005, 23 Pages, 1992/03

PNC-TN8600-92-005.pdf:2.73MB

no abstracts in English

JAEA Reports

None

PNC-TN8600 92-003, 110 Pages, 1992/01

PNC-TN8600-92-003.pdf:8.82MB

no abstracts in English

30 (Records 1-20 displayed on this page)