scholarly journals Civil Engineering Branch of Abiko Research Laboratory, Central Research Institute of Electric Power Industry

1989 ◽  
pp. 41-44
Author(s):  
Hiroyoshi TANAKA
Keyword(s):  
Electric Power ◽  
Research Laboratory ◽  
Civil Engineering ◽  
Electric Power Industry ◽  
Power Industry ◽  
Central Research Institute ◽  
Central Research ◽  
Research Institute

scholarly journals Flaw Assessment Procedure for High-Temperature Reactor Components

1992 ◽  
Vol 114 (2) ◽  
pp. 166-170 ◽  
Author(s):  
R. A. Ainsworth ◽  
M. B. Ruggles ◽  
Y. Takahashi
Keyword(s):  
High Temperature ◽  
Electric Power ◽  
Crack Growth ◽  
Crack Extension ◽  
Creep Crack Growth ◽  
Electric Power Industry ◽  
Central Research Institute ◽  
Assessment Procedure ◽  
Central Research ◽  
Research Institute

An interim high-temperature flaw assessment procedure is described. This is a result of a collaborative effort between Electric Power Research Institute in the US, Central Research Institute of Electric Power Industry in Japan, and Nuclear Electric plc in the UK. The procedure addresses pre-existing defects subject to creep-fatigue loading conditions. Laws employed to calculate the crack growth per cycle are defined in terms of fracture mechanics parameters and constants related to the component material. The crack growth laws may be integrated to calculate the remaining life of a component or to predict the amount of crack extension in a given period. Fatigue and creep crack growth per cycle are calculated separately, and the total crack extension is taken as the simple sum of the two contributions. An interaction between the two propagation modes is accounted for in the material properties in the separate calculations. In producing the procedure, limitations of the approach have been identified. Some of these limitations are to be addressed in an extension of the current collaborative program.

Development, operational experience and implications for future design of FBRS in Japan

1990 ◽  
Vol 331 (1619) ◽  
pp. 355-366
Keyword(s):  
Fuel Cycle ◽  
Electric Power Industry ◽  
Steering Committee ◽  
Central Research Institute ◽  
Operational Experience ◽  
Central Research ◽  
Future Design ◽  
Power Company ◽  
Under Construction ◽  
Research Institute

Joyo, the 100 MW t experimental reactor, has been successfully operated since 1977, and Monju, the 280 MW e prototype FBR, is under construction, with the first criticality planned for 1992. To promote FBR R&D efficiently — including the demonstration FBR (DFBR) programme — a steering committee for R&D was organized in 1986 by the Japan Atomic Power Company, the Power Reactor and Nuclear Fuel Development Corporation, the Japan Atomic Energy Research Institute and the Central Research Institute of Electric Power Industry. A design study of the DFBR is now underway to define its basic specifications by 1990. R&D for Monju, DFBR and future commercial FBRS has been done (1) to improve key technologies developed through the Joyo and Monju programmes; (2) to develop innovative technologies to make FBRS commercial; (3) to promote FBR development in conjunction with the development of the FBR fuel cycle.

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