Title of article
Low alloy steel piping test for fracture criteria of leak before break
Author/Authors
Nakamura، Takao نويسنده , , Koyama، Koji نويسنده , , Muroya، Itaru نويسنده , , Tanaka، Toshihiko نويسنده ,
Issue Information
دوهفته نامه با شماره پیاپی سال 1999
Pages
-146
From page
147
To page
0
Abstract
A total of seven pipe fracture tests were performed to provide the data for establishing fracture criteria of leak before break for the low alloy steel pipe, which is expected to be applied to reactor coolant piping and feedwater piping in advanced PWRs in Japan. Test pipes were 6-inch and 8-inch diameter pipes made of SFVQ1A or STPA24 low alloy steel. A circumferential through-wall crack was introduced at the center of a pipe, and four-point bending load was applied without internal pressure. Stable crack extensions were observed in all of the experiments. The net-section criteria (NSC), R6 method option 2 and option 3 were used to estimate the maximum applied load. The predicted values by three kinds of evaluation methods were compared with the experimental loads. Most of the predicted maximum loads agreed well with the experimental maximum loads within 20% difference. The NSC gave the most accurate prediction but also gave unconservative results in some test cases. The predicted maximum loads by R6 option 2 were conservative in all of the test cases. From the viewpoint of conservativeness R6 method can be used for evaluation of the low alloy steel pipe fracture. Therefore, the leak before break (LBB) concepl could be applied to the protective design standard against pipe break for the material. © 1999 Elsevier Science S.A. All rights reserved.
Keywords
Flow instabilities , Two-phase natural circulation , Semi-closed loop , Expansion tank
Journal title
Nuclear Engineering and Design
Serial Year
1999
Journal title
Nuclear Engineering and Design
Record number
14155
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