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.

Effects of Temperature Changes on Creep Crack Growth for a Low Alloy Butt Weld

2013 ◽  
Author(s):  
Jinhua Shi
Keyword(s):  
High Temperature ◽  
Residual Stresses ◽  
Crack Growth ◽  
Creep Crack Growth ◽  
Welding Residual Stress ◽  
Assessment Procedure ◽  
Butt Weld ◽  
Temperature Changes ◽  
Creep Crack ◽  
Effects Of Temperature

R5 is an assessment procedure for the high temperature response of structures and R5 Volume 7 specifies the creep crack growth assessment for low alloy welds. For high temperature low alloy butt welds, the effects of the welding residual stresses on the creep crack growth for a circumferential defect has been investigated by Shi under a constant temperature of 532.7°C. In addition to the welding residual stresses, it is well known that temperatures also affect significantly creep deformation, creep rupture and accordingly creep crack growth. Hence, in this paper an investigation for the effects of temperature changes on the creep crack growth and also on component remnant lives has been carried out. In this paper, for a typical low alloy butt weld in ½Cr½Mo¼V (‘½CMV’) pipework with 2¼Cr weld metal under a given internal pressure and a bending welding residual stress of 60MPa, a series of creep crack growth analyses have been conducted using the R5 Volume 7 assessment procedure, assuming different operating temperatures during different operating periods. A postulated internal circumferential defect (semi-elliptical surface-breaking surface defect) of 2.3 mm deep by 15 mm long has been used. The investigation results are presented by a series of graphs which show the effects of the temperature changes on the creep crack growth and plant remnant lives for the weld studied. After a detailed discussion, conclusions can be drawn.

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.

scholarly journals On the experimental production of congenital goitre

1916 ◽  
Vol 89 (616) ◽  
pp. 322-327
Keyword(s):  
Central Research Institute ◽  
Central Research ◽  
Experimental Production ◽  
The Past ◽  
White Rats ◽  
Military Duty ◽  
Active Service ◽  
Large Animals ◽  
Research Institute

The experiment herein described was undertaken at the Central Research Institute, Kasauli, India. It commenced on September 6, 1913, and terminated, owing to my recall to military duty for active service, on December 24, 1914. Having been on service for the past 18 months I have not hitherto had an opportunity to report it. Object of the Experiment . Its object was to determine the cause of congenital goitre and the conditions under which it developed in large animals, and to confirm and amplify the results I had obtained by previous experimentation on white rats.

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