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JAEA Reports

Preliminary examination about the seal leak using the photocoagulation resin (Joint research)

Ooka, Makoto; Maekawa, Yasunari; Tomizuka, Chiaki; Murakami, Tomoyuki*; Katagiri, Genichi*; Ozaki, Hiroshi*; Kawamura, Hiroshi

JAEA-Technology 2015-003, 31 Pages, 2015/03

JAEA-Technology-2015-003.pdf:3.95MB

An action for the decommissioning of the Fukushima Daiichi Nuclear Power Station (Tokyo Electric Power Company) is pushed forward now. For fuel debris Remove, it is necessary to fill the Primary Containment Vessel (PCV) with water. Because a coolant leaks out from the PCV, it becomes the most important problem to seal leak the coolant. Nuclear Plant Decommissioning Safety Research Establishment has examined the method of seal leak using the photocoagulation resin. However, originally the photocoagulation resin is used as coating or the painting, and the applicability to seal leak water is unknown. This report describes the result that examined the applicability to seal leak using photocoagulation resin.

Journal Articles

Radwaste reduction technology for spent resins

Aizawa, Hideyuki*; Katagiri, Genichi*; Sano, Kazuya; Higashiura, Norikazu

Fuji Denki Homu Peji and Fuji Denki America Sha Homu Peji (Internet), 11 Pages, 2012/04

In a nuclear power plant, spent IXR (hereafter called SR), low-level radioactive waste, is produced from water purification systems in association with the operation of the plant. These SR are different in a radioactive concentration depending on purification systems, and SR which is relatively higher in the radioactivity concentration is stored in the nuclear power plant. Stored amounts continue to increase year after year. In Japan, it is planned that SR will be buried in the ground in the future as a "waste solid" which is solidified in a specific metal container. In terms of securing long-term soundness of the waste solids, it is said the solidification of the SR is required after stabilization treatment is performed. Moreover, SR with high radioactivity concentration requires higher disposal expenses; therefore, the reduction of the disposal volume is required in terms of cost-cutting. To realize these requirements, processing technologies are required which satisfy both the volume reduction and stabilization of the SR at once. Fuji Electric is continuing to develop LPOP technology and the equipment (FRR: Fuji Resin Reducer) as technologies to respond to these requirements. LPOP treatment is a technology enabling realization of both volume reduction and stabilization of SR which is low-level radioactive waste. Fuji Electric post the overview of LPOP technology and the results of mineralization of ion exchange resin and solidification tests executed for the purpose of evaluating the effect of LPOP treatment aiming the burial disposal on our website.

Journal Articles

Study of LPOP residue on resin mineralization and solidification

Katagiri, Genichi*; Fujisawa, Morio*; Sano, Kazuya; Higashiura, Norikazu

Proceedings of 13th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2010) (CD-ROM), p.125 - 130, 2010/10

Fuji Electric had developed the low pressure oxygen plasma technology for mild decomposition and mineralization of an organic material such as ion exchange resin. This method is suitable for radioactive spent resin volume/weight reduction and stabilization for final disposal. On this process, the ion-exchange resins are vaporized and decomposed into gas-phase with pyrolysis, and then, they are decomposed and oxidized with low-pressure plasma activity based on oxygen. And this process is achieved under moderate condition for radio active waste. (1) incinerate temperature: 400-700 $$^{circ}$$C (2) low-pressure (low-temperature) plasma condition: 10-50 Pa. From the result of this process, named of LPOP(low pressure oxidation process) by the inductively coupled plasma, we have confirmed that the process is applicable for organic fireproof waste including ion-exchange resin, and found that the used resin treatment performance is the same as cold test.

Journal Articles

Development of inspection and repair techniques in reactor vessel of the experimental fast reactor "Joyo" and of visual inspection device to observe in-vessel structures

Saito, Takakazu; Imaizumi, Kazuyuki; Oka, Kiyoshi; Aizawa, Hideyuki*; Katagiri, Genichi*

FAPIG, (179), p.3 - 9, 2009/07

The experimental fast reactor Joyo is the first sodium cooled fast reactor in Japan. In-vessel visual inspections have been conducted with an obstacle on the in-vessel storage rack in Joyo. Because of the high radiation dose in the reactor vessel, radiation-resistant fiberscope was applied to Joyo. The radiation-resistant fiberscope was inserted into the reactor vessel thorough the inspection hole and fuel handling hole on rotating plugs. In order to observe the top of the subassemblies and in-vessel storage rack, an I-shape device which had a downward and side view monitoring radiation-resistant fiberscopes was used. To observe the bottom face of the upper core structure, a remote handling visual device whose tip could bend into an L-shape was developed to insert the radiation-resistant fiberscope into the 70 mm gap between the bottom of the upper core structure and the top of the subassemblies. The observations of the top of the subassemblies and in-vessel storage rack were conducted from October 2007 to February 2008. The bottom face of the upper core structure was observed in July 2008. The number of photographs of the entire bottom face of the upper core structure reached approximately 35,000. Confirmation was made that the remote handling device equipped with the radiation-resistant fiberscope would achieve the expected performance. These observations results provided useful information on incident investigations. In addition, fundamental findings and the experience gained during this study, which included the design of equipment, operating procedures, resolution, lighting adjustments, photograph composition and the durability of the radiation-resistant fiberscope under radiation exposure, provided valuable insights into possible further improvements and verifications for in-vessel visual observation techniques in an sodium fast reactor.

Oral presentation

Inspection and repair techniques in reactor vessel of sodium cooled fast reactor, 5; Visual inspection and obstacle removal method in reactor vessel of the experimental fast reactor Joyo

Ito, Hideaki; Nagai, Akinori; Tobita, Shigeharu; Ashida, Takashi; Kaito, Yasuaki; Katagiri, Genichi*; Kodama, Takemitsu*; Yoshimura, Tetsuji*

no journal, , 

no abstracts in English

Oral presentation

Inspection and repair techniques in reactor vessel of sodium cooled fast reactor, 2-2; Development of visual inspection device to observe in-vessel structures

Imaizumi, Kazuyuki; Tobita, Shigeharu; Saito, Takakazu; Katagiri, Genichi*; Aizawa, Hideyuki*; Yaginuma, Yoshihiro*

no journal, , 

no abstracts in English

Oral presentation

Basic test for making Waste package for Spent resin disposal

Otani, Hiroshi; Higashiura, Norikazu; Mizui, Hiroyuki; Endo, Nobuyuki*; Katagiri, Genichi*; Oshio, Tadashi*; Ogawa, Hideo*

no journal, , 

no abstracts in English

Oral presentation

Basic test for making waste package for spent resin disposal, 1; Volume reduction and stabilization process by low pressure oxygen plasma process for spent resin

Mizui, Hiroyuki; Otani, Hiroshi; Higashiura, Norikazu; Onozaki, Kimihiro*; Katagiri, Genichi*; Endo, Nobuyuki*; Ogawa, Hideo*; Kaneda, Yoshihisa*

no journal, , 

The applicable prospect for spent resin disposal including inhibitor was acquired by basic test of using low pressure oxygen plasma method.

Oral presentation

Remote technology development for function advancement of research base, 5; Applicability examination for leakage sealing using the photo-curable resin

Shimada, Kozue; Ooka, Makoto; Maekawa, Yasunari; Tomizuka, Chiaki; Murakami, Tomoyuki*; Katagiri, Genichi*; Ozaki, Hiroshi*; Aoyagi, Katsuhiro*; Kawamura, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

Development of a water stoppage technique using the photo-curable resin for decommissioning

Shimada, Kozue; Ooka, Makoto; Maekawa, Yasunari*; Tomizuka, Chiaki; Katagiri, Genichi*; Aoyagi, Katsuhiro*; Shibata, Takuya; Koyama, Shinichi

no journal, , 

Oral presentation

Applicability examination for water stoppage using the photo-curable resin; Development of water stoppage technique by the improved photo-curable resin

Shimada, Kozue; Tomizuka, Chiaki; Shibata, Takuya; Ooka, Makoto; Maekawa, Yasunari*; Aoyagi, Katsuhiro*; Shinoki, Masatoshi*; Katagiri, Genichi*; Ozaki, Hiroshi*; Koyama, Shinichi

no journal, , 

no abstracts in English

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