Published October 1997 | Version v1
Journal article

Development of new Z-factors for the evaluation of the circumferential surface crack in nuclear pipes

  • 1. Korea Inst. of Nucl. Safety, Taejon (Korea, Republic of). Mach. Eng. Group
  • 2. Engineering Mechanics Group, Battelle Memorial Institute, 505 King Avenue, Columbus, OH 43201 (United States)

Description

The purpose of this study is to develop new Z-factors to evaluate the behavior of a circumferential surface crack in nuclear pipe. Z-factor is a load multiplier used in the Z-factor method, which is one of the ASME Code Sec. XI's recommendations for the estimation of a surface crack in nuclear pipe. It has been reported that the load carrying capacities predicted from the current ASME Code Z-factors, are not well in agreement with the experimental results for nuclear pipes with a surface crack. In this study, new Z-factors for ferritic base metal, ferritic submerged arc welding (SAW) weld metal, austenitic base metal, and austenitic SAW weld metal are obtained by use of the surface crack for thin pipe (SC.TNP) method based on GE/EPRI method. The desirability of both the SC.TNP method and the new Z-factors is examined using the results from 48 pipe fracture experiments for nuclear pipes with a circumferential surface crack. The results show that the SC.TNP method is good for describing the circumferential surface crack behavior and the new Z-factors are well in agreement with the measured Z-factors for both ferritic and austenitic pipes. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
174
Journal Issue
1
Journal Page Range
p. 3-15.
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
Japan-Korea workshop in the integrity of nuclear components.
Dates
8 May 1996.
Place
Daejon (Korea, Republic of).

Optional Information

Notes
28 refs.