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Journal Articles

Replacement of the glove port equipped with glove box in Nuclear Fuel Reprocessing Facility

Horigome, Kazushi; Taguchi, Shigeo; Nishida, Naoki; Goto, Yuichi; Inada, Satoshi; Kuno, Takehiko

Nihon Hozen Gakkai Dai-14-Kai Gakujutsu Koenkai Yoshishu, p.381 - 384, 2017/08

no abstracts in English

Journal Articles

Design and application of greenhouse on the maintenance of analytical machineries in Tokai Reprocessing Plant

Suzuki, Yoshimasa; Tanaka, Naoki; Goto, Yuichi; Inada, Satoshi; Kuno, Takehiko

Nihon Hozen Gakkai Dai-14-Kai Gakujutsu Koenkai Yoshishu, p.385 - 389, 2017/08

Greenhouse is used in order to prevent diffusion of radioactive materials on the maintenance of machineries and decomposition of the analytical equipment such as glove box in Tokai Reprocessing Plant (TRP). The specifications of the greenhouse change depending on a risk of the radiation exposure, operation and environment. Design and application of original greenhouses in the analytical laboratory of TRP is summarized.

Journal Articles

Industry development activities and applied laser research activities at Fukui branch of Japan Atomic Energy Agency

Furusawa, Akinori; Takenaka, Yusuke*; Nishimura, Akihiko; Mizutani, Haruki; Muramatsu, Toshiharu

Nihon Hozen Gakkai Dai-14-Kai Gakujutsu Koenkai Yoshishu, p.479 - 480, 2017/08

Industry development activities on applied laser research held at Fukui branch of Japan Atomic Energy Agency are reported. Industry development is inevitable in long-term vision and strategy for developing maintenance technology and establishing decommissioning technology. Fukui branch of JAEA has organized public seminar offering businesses to promote these activities and technology exchange for years. Here some examples offered in the current seminar are introduced concerning with laser technology. Finally, our goal and important point of view are discussed.

Oral presentation

Proposal of maintenance management of nuclear power plants at R&D stage by taking account of their features, 3; Application to piping support

Aizawa, Kosuke; Takaya, Shigeru; Chikazawa, Yoshitaka; Tagawa, Akihiro; Kubo, Shigenobu

no journal, , 

One of important mission of nuclear power plants (NPP) at R&D stage is to develop maintenance program for commercial reactors step by step securing safety. Basic principles of maintenance management for NPP at R&D stage were proposed. In this paper, applications for maintenance program on piping support of prototype sodium cooled fast breeder reactor Monju are studied on the basis of the proposed basic principles of maintenance management for NPP at R&D stage.

Oral presentation

Study on a method for identifying degradation mechanisms to be validated in maintenance management of R&D-level nuclear power plants using the PIRT process

Takaya, Shigeru; Chikazawa, Yoshitaka; Tanaka, Masaaki

no journal, , 

In a previous paper, the authors discussed maintenance management suitable to R&D-level nuclear power plants, and made proposals. One of key proposals was to enhance knowledge on potential degradation mechanisms specific to a new reactor type by accumulating operational experience. It was noted that validation of R&D knowledge in actual plant conditions is important. In this study, a method for identifying degradation mechanisms to be validated by the PIRT (Phenomena Identification and Ranking Table) process is proposed to develop effective maintenance plans of R&D-level nuclear power plants based on the graded approach. Furthermore, the applicability of the proposed method is illustrated by an example of application to MONJU that is an R&D-level nuclear power plant of sodium-cooled fast reactors.

Oral presentation

Proposal of maintenance management of nuclear power plants at R&D stage by taking account of their features, 4; Case study on sodium valves

Chikazawa, Yoshitaka; Takaya, Shigeru; Aizawa, Kosuke; Tagawa, Akihiro

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, maintenance program for sodium valves are investigated.

Oral presentation

Evaluation of the sustainability of compressive residual stress by introduced a stress improvement method, 1; Development of analysis method of the shot peening using idealized explicit FEM

Yamada, Yusuke*; Shibahara, Masakazu*; Ikushima, Kazuki*; Kitani, Yuji*; Nishikawa, Satoru*; Furukawa, Takashi*; Akita, Koichi; Suzuki, Hiroshi; Morooka, Satoshi

no journal, , 

no abstracts in English

Oral presentation

Evaluation of the sustainability of compressive residual stress by introduced a stress improvement method, 2; Residual stress change of welded joint with shot peening by thermal cycle and stress loading

Nishikawa, Satoru*; Furukawa, Takashi*; Akita, Koichi; Suzuki, Hiroshi; Morooka, Satoshi; Harjo, S.; Shibahara, Masakazu*; Ikushima, Kazuki*; Kitani, Yuji*; Yamada, Yusuke*

no journal, , 

no abstracts in English

Oral presentation

Evaluation of the sustainability of compressive residual stress by introduced a stress improvement method, 3; Study of the relevance of shot peening analysis method by IEFEM and the sustainability of compressive residual stress

Kitani, Yuji*; Shibahara, Masakazu*; Ikushima, Kazuki*; Yamada, Yusuke*; Nishikawa, Satoru*; Furukawa, Takashi*; Akita, Koichi; Suzuki, Hiroshi; Morooka, Satoshi

no journal, , 

no abstracts in English

Oral presentation

Study of behavior to relieve residual stress at the time of the shot peening

Kitani, Yuji*; Shibahara, Masakazu*; Ikushima, Kazuki*; Yamada, Yusuke*; Nishikawa, Satoru*; Furukawa, Takashi*; Akita, Koichi; Suzuki, Hiroshi; Morooka, Satoshi

no journal, , 

no abstracts in English

Oral presentation

For discussions with the public for the safety of nuclear power; Risks for judgments

Noguchi, Kazuhiko*; Miyano, Hiroshi*; Muramatsu, Ken*; Narumiya, Yoshiyuki*; Takata, Takashi; Muta, Hitoshi*; Itoi, Tatsuya*; Matsumoto, Masaaki*; Matsunaga, Yoko*; Sugiyama, Kenichiro*

no journal, , 

The risk is used for an index to judge. The risk to be considered varies according to the purpose of the judgment. The analysis of the risk needs the knowledge of the nuclear energy system and society.

Oral presentation

For discussions with the public for the safety of nuclear power; Their trust on safety

Miyano, Hiroshi*; Muramatsu, Ken*; Noguchi, Kazuhiko*; Narumiya, Yoshiyuki*; Takata, Takashi; Muta, Hitoshi*; Itoi, Tatsuya*; Matsumoto, Masaaki*; Matsunaga, Yoko*; Sugiyama, Kenichiro*

no journal, , 

In considering nuclear safety, it is an important task to clarify the relationship with "peace of mind" that is the heart of people. What is the state that scientific safety is something that people feel safe? We considered the relationship between quantified risk and safety, and ways to acquire peace of mind. We analyzed the thresholds of safety risks as a social common, showed a safe condition, and showed the importance of forming a consensus to obtain peace of mind.

Oral presentation

For discussions with the public for the safety of nuclear power; Social risk and nuclear risk

Matsumoto, Masaaki*; Miyano, Hiroshi*; Noguchi, Kazuhiko*; Muramatsu, Ken*; Narumiya, Yoshiyuki*; Takata, Takashi; Muta, Hitoshi*; Itoi, Tatsuya*; Matsunaga, Yoko*; Sugiyama, Kenichiro*

no journal, , 

In society, understanding of risk is various. We will show how to understand risk and describe how to face risks in the society. Individual risks are accepted by individuals, but it is necessary for society to construct a structure in society that allows risks to be tolerated by society. For that purpose, we also describe what social risk is and how society and individuals face social risks and how to choose risks to accept. We consider not only the concept of nuclear risk but also how nuclear risk should be accepted from the viewpoint of disaster prevention for the public.

Oral presentation

For discussions with the public for the safety of nuclear power; Discussion with the public

Matsunaga, Yoko*; Miyano, Hiroshi*; Noguchi, Kazuhiko*; Muramatsu, Ken*; Narumiya, Yoshiyuki*; Takata, Takashi; Muta, Hitoshi*; Itoi, Tatsuya*; Matsumoto, Masaaki*; Sugiyama, Kenichiro*

no journal, , 

After Fukushima Daiichi nuclear accident, it becomes more important risk communication with the public. In discussions with the public in nuclear safety, communication and discussions on risks that not only nuclear risks also social risks are important. Differences in viewpoints, understanding, and thought about risks become communication difficult. We need to discuss risks fairly, appropriately with the public and reduce total social risks.

Oral presentation

For discussions with the public for the safety of nuclear power; Risk assessment for nuclear safety and application to external event

Takata, Takashi; Miyano, Hiroshi*; Noguchi, Kazuhiko*; Muramatsu, Ken*; Narumiya, Yoshiyuki*; Muta, Hitoshi*; Itoi, Tatsuya*; Matsumoto, Masaaki*; Matsunaga, Yoko*

no journal, , 

A considering nuclear safety, it is an important task to clarify the relationship with "peace of mind" that is the heart of people. In this paper, a fundamental methodology of risk assessment for nuclear safety is introduced based on a probabilistic risk assessment (PRA) method. Furthermore, an application of the methodology for an external event is also discussed.

Oral presentation

For discussions with the public for the safety of nuclear power; Applying risk information to prevention/mitigation of SA

Narumiya, Yoshiyuki*; Miyano, Hiroshi*; Noguchi, Kazuhiko*; Muramatsu, Ken*; Takata, Takashi; Muta, Hitoshi*; Itoi, Tatsuya*; Matsumoto, Masaaki*; Matsunaga, Yoko*

no journal, , 

In order to grasp efficiency of risk information, we tried to apply an insight of PRA to considering of severe accidents; TMI, Chernobyl, and Fukushima Dai-ichi. Based on this analysis, three points are disclosed. At first, PRA can product adequate countermeasures for low-likelihood events; huge earthquake or Tsunami. Next, PRA can prove weak points in design or operation reasonably. Third point is safety culture. PRA and safety culture are seemed to be connected deeply. These analyses revealed PRA is one of the most efficient and systematic risk analysis methods to prevent/mitigate severe accidents.

Oral presentation

For discussions with the public for the safety of nuclear power; Various patterns of risk application method and examples

Narumiya, Yoshiyuki*; Miyano, Hiroshi*; Noguchi, Kazuhiko*; Muramatsu, Ken*; Takata, Takashi; Muta, Hitoshi*; Itoi, Tatsuya*; Matsumoto, Masaaki*; Matsunaga, Yoko*

no journal, , 

Target of PRA is not calculating PRA to get CDF/CFF, but providing significant and useful information from PRA results for risk-informed activities. Lot of risk applications have been implemented these about 20 years in US. After Fukushima Dai-ichi accidents, Japanese Nuclear Regulation Authority provided new regulatory requirements about external events and beyond design events. And Risk Application faces full-scale implementation. In this report, several methods of risk application are showed with adequate risk indexes. Two examples of risk application, risk-informed shutdown management and RI-ISI, are provided. The explanation about Risk Informed Decision-Making Process is made.

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