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Journal Articles

Study on loss-of-cooling and loss-of-coolant accidents in spent fuel pool, 8; Safety margin of spent fuel in large LOCA event by the simple assessment method

Someya, Takayuki*; Chitose, Hiromasa*; Watanabe, Satoshi*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 9 Pages, 2019/05

In this study, CFD analysis has been conducted for the assessment of spent fuel integrity in large LOCA event and the maximum temperature of spent fuel assemblies has been evaluated. Then, it has been compared with the result of the simple assessment method. As a case study, additional CFD analysis has been conducted, where water level in SFP decreases to the Bottom of Active Fuel (BAF) due to boil-off. Since this scenario might be more severe than large LOCA scenario, the number of spent fuel assemblies, their decay heat and loading pattern to maintain spent fuel integrity are investigated.

Journal Articles

The Influences of Pu and Zr on the melting temperatures of the UO$$_{2}$$-PuO$$_{2}$$-ZrO$$_{2}$$ pseudo-ternary system

Morimoto, Kyoichi; Hirooka, Shun; Akashi, Masatoshi; Watanabe, Masashi; Sugata, Hiromasa*

Journal of Nuclear Science and Technology, 52(10), p.1247 - 1252, 2015/10

 Times Cited Count:4 Percentile:33.25(Nuclear Science & Technology)

As a part of decommissioning plan of the damaged reactors at Fukushima Daiichi Nuclear Power Plant, some strategies for removing of debris from the reactors are discussed. In these considerations, it is necessary to predict a melt progression during the severe accident based on theoretical evidences. Melting temperature is one of the most important thermal characteristics to analyse a melt progression during the severe accident. In this study, the melting temperatures of specimens of U, Pu and Zr mixed oxide prepared as simulated debris were measured by the thermal arrest technique. From the results of this measurement, the influences of Pu$$^{-}$$ and Zr$$^{-}$$ contents on the melting temperature of the simulated debris were evaluated.

Journal Articles

The IRAC code system to calculate activation and transmutation in the TIARA Facility

Tanaka, Susumu; Fukuda, Mitsuhiro; Nishimura, Koichi; Hosono, Masakazu; Watanabe, Hiromasa; Yamano, Naoki*

Journal of Nuclear Science and Technology, 37(Suppl.1), p.840 - 844, 2000/03

no abstracts in English

JAEA Reports

IRACM: A Code system to calculate induced radioactivity produced by ions and neutrons

; Fukuda, Mitsuhiro; ; Watanabe, Hiromasa; Yamano, Naoki*

JAERI-Data/Code 97-019, 91 Pages, 1997/05

JAERI-Data-Code-97-019.pdf:2.58MB

no abstracts in English

Journal Articles

Radiation protection in accelerator facilities

Tanaka, Ryuichi; Yotsumoto, Keiichi; Watanabe, Hiromasa

Radioisotopes, 45(3), p.213 - 220, 1996/03

no abstracts in English

Journal Articles

Utilization of TIARA facilities

Watanabe, Hiromasa; Tanaka, Susumu; Nishimura, Koichi; Hosono, Masakazu

JAERI-Review 95-019, p.245 - 246, 1995/10

no abstracts in English

Journal Articles

Advanced radiation technology by using ion beams, 3; TIARA facilities, 3.1, Utilization of TIARA facilities

Watanabe, Hiromasa

Genshiryoku Kogyo, 40(2), p.12 - 15, 1994/00

no abstracts in English

Journal Articles

A New radioisotope-production research facility utilizing ion beams from AVF cyclotron

Sekine, Toshiaki; Izumo, Mishiroku; Matsuoka, Hiromitsu; Kobayashi, Katsutoshi; ; Osa, Akihiko; Koizumi, Mitsuo; Motoishi, Shoji; Hashimoto, Kazuyuki; ; et al.

Proc. of the 5th Int. Workshop on Targetry and Target Chemistry, 0, p.347 - 352, 1994/00

no abstracts in English

Journal Articles

Development of IRAC code system to calculate induced radioactivity produced by ions and neutrons

Tanaka, Susumu; Fukuda, Mitsuhiro; Nishimura, Koichi; Yokota, Wataru; Kamiya, Tomihiro; Watanabe, Hiromasa; Yamano, Naoki*; ;

Proc. of the 8th Int. Conf. on Radiation Shielding, 0, p.965 - 971, 1994/00

no abstracts in English

Journal Articles

Radiation monitoring system in cyclotron facility at TIARA

Nakamura, Yoshiteru; ; Nishimura, Koichi; Watanabe, Hiromasa; ; *; *

Proc. of the 9th Symp. on Accelerator Science and Technology, p.434 - 436, 1993/00

no abstracts in English

Journal Articles

Radiation safety of Takasaki ion accelerators for advanced radiation application in JAERI

Watanabe, Hiromasa; Tanaka, Susumu;

Hoken Butsuri, 26, p.395 - 404, 1991/00

no abstracts in English

Journal Articles

Quick replacement technology using SMA driver for high load core elements of fusion reactor

*; *; *; *; *; *; Iida, Hiromasa; Hoshiya, Taiji; *; *; et al.

Fusion Technology 1988, p.1806 - 1810, 1989/00

no abstracts in English

Oral presentation

Advanced development of a laser endoscopy for FLPC of TTTS

Oka, Kiyoshi; Nakamura, Tetsuya*; Ueda, Hirohisa*; Toriya, Tomoaki*; Tsumanuma, Koji*; Naganawa, Akihiro*; Watanabe, Shinsuke*; Ishiyama, Akihiko*; Yamashita, Hiromasa*; Chiba, Toshio*

no journal, , 

no abstracts in English

Oral presentation

Construction and commissioning of a small non-circular tokamak

Hatakeyama, Shoichi*; Miura, Hiromasa*; Yao, Z.*; Tsutsui, Hiroaki*; Iio, Shunji*; Shibata, Yoshihide; Ono, Noriyasu*; Watanabe, Kiyomasa*; Akiyama, Tsuyoshi*; Nakamura, Kazuo*

no journal, , 

no abstracts in English

Oral presentation

Study on improvement of safety for accident conditions in spent fuel pool, 6; Issues and procedures on the effectiveness evaluation for SFP safety measures

Chitose, Hiromasa*; Watanabe, Satoshi*; Sadamatsu, Hideaki*; Iwata, Yutaka*; Kaji, Yoshiyuki; Nemoto, Yoshiyuki

no journal, , 

We researched the recent enhancements of regulations and solutions related Spent Fuel Pool safety and reported the analytical results about problems and evaluation procedures related effectiveness evaluation of safety measures.

15 (Records 1-15 displayed on this page)
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