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Journal Articles

Development of radiation-resistant in-water wireless transmission system

Takeuchi, Tomoaki; Otsuka, Noriaki; Shibagaki, Taro*; Komanome, Hirohisa*; Ueno, Shunji*; Tsuchiya, Kunihiko

Nippon Hozen Gakkai Dai-13-Kai Gakujutsu Koenkai Yoshishu, p.379 - 386, 2016/07

no abstracts in English

Journal Articles

Cause investigation for thinning of anchor bolts and gaps between anchor bolt nuts and a flange plate at the JMTR hot laboratory exhaust stack

Shibata, Akira; Kitagishi, Shigeru; Watashi, Katsumi; Matsui, Yoshinori; Omi, Masao; Sozawa, Shizuo; Naka, Michihiro

Nippon Hozen Gakkai Dai-13-Kai Gakujutsu Koenkai Yoshishu, p.290 - 297, 2016/07

The exhaust stack of Japan Materials Testing Reactor Hot laboratory is a part of gaseous waste treatment system. It was built in 1970 and is 40 m in height. In 2015, thinning was found at some anchor bolts on base of the stack. When thinning of anchor bolts were investigated, gaps between anchor bolt nuts and flange plate was found. JAEA removed steel cylinder of stack which is 33 m in height for safety. In the end of investigation, thinning was found in all anchor bolts of the stack. Cause investigation for the thinning and the gaps were performed. It is concluded that the thinning was caused by water infiltration over a long period of time and the gaps were caused by elongation of thinning part of anchor bolts by the 2011 earthquake off the Pacific coast of Tohoku.

Journal Articles

Gamma irradiation effects of image sensor for radiation-resistant camera

Takeuchi, Tomoaki; Otsuka, Noriaki; Tsuchiya, Kunihiko; Tanaka, Shigeo*; Ozawa, Osamu*; Komanome, Hirohisa*; Watanabe, Takashi*; Ueno, Shunji*

Nippon Hozen Gakkai Dai-13-Kai Gakujutsu Koenkai Yoshishu, p.391 - 394, 2016/07

no abstracts in English

Journal Articles

R&D of high-temperature resistance type mineral insulated cable for sever accident

Miura, Kuniaki*; Shibata, Hiroshi; Onizawa, Tatsuya*; Nakano, Hiroko; Takeno, Naofumi*; Takeuchi, Tomoaki; Tsuchiya, Kunihiko

Nippon Hozen Gakkai Dai-13-Kai Gakujutsu Koenkai Yoshishu, p.387 - 390, 2016/07

no abstracts in English

Journal Articles

Replacement of the glove box panel in Nuclear Fuel Reprocessing Facility

Masui, Kenji; Yamamoto, Masahiko; Kuno, Takehiko; Surugaya, Naoki

Nippon Hozen Gakkai Dai-13-Kai Gakujutsu Koenkai Yoshishu, p.25 - 30, 2016/07

no abstracts in English

Journal Articles

Physical property of seal-gasket for glove box panel in reprocessing facilities

Goto, Yuichi; Yamamoto, Masahiko; Kuno, Takehiko; Surugaya, Naoki

Nippon Hozen Gakkai Dai-13-Kai Gakujutsu Koenkai Yoshishu, p.31 - 34, 2016/07

Chloroprene rubber gaskets are often used to seal the glove box body and its panels. Such gaskets are deformed with compressive pressure and its elastic restoring force keeps sealing property. Therefore, gaskets play an important role in glove box sealing. However, physical properties of those used in glove box have not reported so far. In this study, hardness, elongation, tensile strength and compression set are investigated and its sealing performances are evaluated. The gaskets samples are taken from the glove box, which is used for 37 years. It is found that hardness, elongation and tensile strength of gaskets are changed due to the aging but its values are within the specification of chloroprene rubber. Also, the compression-set is less than the value that sealing performance is decreased. The results show that even the gaskets are used for long time, it has the property to keep sealing performances of glove box.

Journal Articles

Status of R&D of high-performance monitoring system under sever accident

Tsuchiya, Kunihiko; Takeuchi, Tomoaki; Komanome, Hirohisa*; Miura, Kuniaki*; Araki, Masanori; Ishihara, Masahiro

Nippon Hozen Gakkai Dai-13-Kai Gakujutsu Koenkai Yoshishu, p.375 - 378, 2016/07

no abstracts in English

Oral presentation

R&D program of maintenance technologies for the fast reactors in the sodium engineering research facility

Ueda, Masashi; Yamaguchi, Toshihiko; Saruta, Koichi

no journal, , 

no abstracts in English

Oral presentation

Proposal of maintenance management of nuclear power plants at R&D stage by taking account of their features, 1; Basic requirements

Takaya, Shigeru; Chikazawa, Yoshitaka; Hayashida, Kiichi*; Tagawa, Akihiro; Kubo, Shigenobu; Yamashita, Atsushi*

no journal, , 

A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage was first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed.

Oral presentation

Proposal of maintenance management of nuclear power plants at R&D stage by taking account of their features, 2; Case study

Chikazawa, Yoshitaka; Takaya, Shigeru; Hayashida, Kiichi*; Tagawa, Akihiro; Kubo, Shigenobu; Yamashita, Atsushi*

no journal, , 

A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage were first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. In this paper, requirements on maintenance program of NPP at R&D stage were clarified and an example that the proposal was applied to setting maintenance program of sodium-cooled fast reactor was presented.

Oral presentation

Provision of laser coating irradiation conditions with a computational science simulation code SPLICE

Muramatsu, Toshiharu; Yoshiuji, Takahiro

no journal, , 

A general-purpose three-dimensional thermohydraulics numerical simulation code SPLICE was developed at Japan Atomic Energy Agency and designed to deal with gas-liquid-solid consolidated incompressible viscous flows with a phase change process in various laser applications, such as welding, coating, cutting, etc. The result obtained from laser coating simulations is very encouraging in the sense that the SPLICE code would be used as one of efficient tools to provide the laser coating irradiation conditions.

Oral presentation

EMAT-guided wave approach for detecting and quality evaluation of the laser beam butt welding line on the inner surface of the steel pipe

Furusawa, Akinori; Nishimura, Akihiko; Torimoto, Kazuhiro; Takenaka, Yusuke*; Saijo, Shingo*; Toyama, Ryoji*

no journal, , 

The aim of this work presented here is to investigate the applicability of the guided wave testing to detect and evaluate the quality of laser beam butt welding line. First, four test pipes were prepared. All of the pipes were laser beam butt welded from inside of the pipe using laser torch. Two pipes of them were high-quality welded, the others were low-quality. Two different pipe-wall-thicknesses were in each quality. Secondly, Laser beam butt welding line detection and the quality evaluation experiments were performed. T(0,1) mode guided wave was excited and received by electromagnetic acoustic transducer array. Finally, the experimental results were analyzed and issues concerning with the applicability of the guided wave testing to detection and quality evaluation of the laser butt welding line were discussed.

Oral presentation

Design study on fuel and reactor core for plutonium burner high temperature gas-cooled reactor

Goto, Minoru; Inaba, Yoshitomo; Fukaya, Yuji; Ueta, Shohei; Aihara, Jun; Tachibana, Yukio; Kunitomi, Kazuhiko

no journal, , 

A concept of a plutonium burner HTGR (High Temperature Gas-cooled Reactor) with a high nuclear proliferation resistance has been proposed by Japan Atomic Energy Agency. In addition to the high nuclear proliferation resistance, in order to attain the high burn-up, we propose to introduce a PuO$$_{2}$$-YSZ (Yttria Stabilized Zirconia) fuel kernel with ZrC coating to the plutonium burner HTGR. In this study, we conduct design of the coated fuel particle and of the reactor core to confirm the feasibility of the plutonium burner HTGR. This study was started in FY2014 and will be completed in FY2017, and the implementation is on schedule. This paper describes the implementation of the first and the second year.

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