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Journal Articles

Meanings of international collaboration for next generation reactors and importance in energy supply

Suzuki, Yasufumi

Genshiryoku eye, 50(6), p.10 - 11, 2004/06

no abstracts in English

Journal Articles

Thermal-hydraulic characteristics of a next-generation reactor relying on steam generator secondary side cooling for primary depressurization and long-term passive core cooling

Yonomoto, Taisuke; ; Anoda, Yoshinari

Nucl. Eng. Des., 185(1), p.83 - 96, 1998/00

 Times Cited Count:3 Percentile:31.81(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Core design for the next generation sodium-cooled fast reactor, 1; Core performance requirements and design conditions

Oki, Shigeo; Chikazawa, Yoshitaka; Kubo, Shigenobu; Hibi, Koki*; Kan, Taro*

no journal, , 

no abstracts in English

Oral presentation

Core design for the next generation sodium-cooled fast reactor, 2; Reference core design

Tsuboi, Toru*; Moriwaki, Hiroyuki*; Ogura, Masashi*; Hibi, Koki*; Maeda, Seiichiro; Ohgama, Kazuya; Chikazawa, Yoshitaka; Oki, Shigeo

no journal, , 

no abstracts in English

Oral presentation

Core design for the next generation sodium-cooled fast reactor, 3; Design optimization for the core arrangement

Moriwaki, Hiroyuki*; Ogura, Masashi*; Kan, Taro*; Oki, Shigeo

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Shielding design in the reactor vessel for the next generation sodium-cooled fast reactor, 2; Improvement of shielding design methods for optimizing radial neutron shieldings

Hibi, Koki*; Fukuchi, Ikuo*; Masuyama, Daisuke*; Sugino, Kazuteru; Oki, Shigeo

no journal, , 

no abstracts in English

Oral presentation

Fuel and NFBC assemblies design for the next generation sodium-cooled fast reactor, 2; Optimization of a radial shielding structure

Saito, Hiroyuki*; Higurashi, Koichi*; Masuyama, Daisuke*; Oki, Shigeo; Ohgama, Kazuya; Maeda, Seiichiro

no journal, , 

no abstracts in English

Oral presentation

Availability evaluation of passive reactor shut-down system in partial load operating conditions of the next generation sodium-cooled fast reactor

Saito, Hiroyuki*; Yamada, Yumi*; Oyama, Kazuhiro*; Matsunaga, Shoko*; Kubo, Shigenobu; Yamano, Hidemasa

no journal, , 

The effectiveness of self-actuated shutdown structure (SASS) for representative LOF-type ATWS event in a low-power operation was confirmed after the definition of a response time by three-dimensional thermal hydraulics analysis for its modified structure in order to improve the response characteristics of SASS.

Oral presentation

Oral presentation

Development of an automatic maintenance scheduling method for nuclear power plants using integer programming

Hashidate, Ryuta; Yada, Hiroki; Takaya, Shigeru; Ito, Mari*; Suzuki, Masaaki*

no journal, , 

In order to develop next-generation reactor with excellent safety and economic efficiency, it is necessary to evaluate the maintenance schedule from design stage. The maintenance schedule directly affects plant availability and operation costs. If there is a problem in the design, it is necessary to take countermeasures and improve the design to enable rational maintenance. Therefore, we propose an automatic maintenance scheduling method using integer programming.

Oral presentation

Design of a low sodium void reactivity core concept of tank-type sodium-cooled fast reactor

Hasegawa, Takashi*; Kan, Taro*; Moriwaki, Hiroyuki*; Tokizaki, Minako*; Yamano, Hidemasa; Takano, Kazuya

no journal, , 

no abstracts in English

Oral presentation

Development of a method for extracting maintenance preconditions by using the graph structure and application to maintenance scheduling

Hashidate, Ryuta; Kondo, Yuki; Yada, Hiroki; Takaya, Shigeru; Enuma, Yasuhiro

no journal, , 

In this study, we propose a new method for extracting maintenance preconditions. Graph structures are used to represent relationship among SSCs. Maintenance preconditions are extracted by analyzing the graph structures. Furthermore, we propose an automatic maintenance scheduling method using extracted maintenance preconditions. Design issues could be extracted based on the created maintenance schedule. A simple example is presented to illustrate the proposed method.

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