JAEA
  • help
  • PC | SP
  • JP | EN
          
Refine your search：     
Report No.
 - 
Clear All
Search Results: Records 1-5 displayed on this page of 5
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Application of a fiber optic grating strain sensor for the measurement of strain under irradiation environment

Kaji, Yoshiyuki; Matsui, Yoshinori; Kita, Satoshi; Ide, Hiroshi; Tsukada, Takashi; Tsuji, Hirokazu

Nuclear Engineering and Design, 217(3), p.283 - 288, 2002/09

https://doi.org/10.1016/S0029-5493(02)00197-8
 Times Cited Count：4 Percentile：29.25(Nuclear Science & Technology)

In the Japan Atomic Energy Research Institute (JAERI), in-pile strain measurement techniques have been developed using the Japan Materials Testing Reactor (JMTR). In order to evaluate the performance of fiber optic grating sensors under irradiation environment, heat-up and performance tests at elevated temperatures before irradiation and in-pile tests were performed in JMTR. It was determined that it is possible to measure strain under irradiation environment below 1$$times$$1023n/m$$^{2}$$ (E$$>$$1MeV) by a fiber optic grating sensor, because in-pile temperature characteristics were in good agreement with out-of-pile test results.

JAEA Reports

Improvement of the level of safety for future FBR by means of passive safety features; 1:Assessment of passive safety measures and proposal of their R&D programs

; ; Uto, Nariaki; Yamaguchi, Akira; Kamide, Hideki; Ohshima, Hiroyuki; Hayashi, Kenji

PNC TN9410 94-235, 135 Pages, 1994/08

PNC-TN9410-94-235.pdf:6.67MB

In this report passive prevention and mitigation measures with regard to core disruptive accident in future large scale liquid metal cooled fast breeder reactors are discussed and assessed. First the criteria for the assessment of passive safety measures are proposed, and the commonly proposed passive prevention and mitigation measures are briefly reviewed. Then innovative prevention and mitigation measures are newly proposed to provide additional mechanisms to limit the core damage or to prevent a recriticality event during the core disruption process. After assessing these passive measures based on the proposed criteria, appropriate combinations of the measures are recommended. Further, required R&D programs to confirm their effectiveness are described including necessity of a new in-pile experimental program.

Oral presentation

Analyses of in-pile experiments by an analysis code on initiating phase of core disruptive accident in sodium cooled fast reactors,1; Summary of SAS4A code and CABRI in-pile experiments

Fukano, Yoshitaka; Imaizumi, Yuya; Yoshioka, Naonori*; Akahori, Hisashi*

no journal, , 

no abstracts in English

Oral presentation

Analyses of in-pile experiments by an analysis code on initiating phase of core disruptive accident in sodium cooled fast reactors, 2; Analysis of LTX test

Akahori, Hisashi*; Fukano, Yoshitaka

no journal, , 

no abstracts in English

Oral presentation

Analyses of in-pile experiments by an analysis code on initiating phase of core disruptive accident in sodium cooled fast reactors, 3 Analysis of LT4 test

Yoshioka, Naonori*; Fukano, Yoshitaka

no journal, , 

no abstracts in English

5 (Records 1-5 displayed on this page)
  • 1