Published October 2010 | Version v1
Miscellaneous

Development of Dissimilar Metal Weld Performance Demonstration System

  • 1. KEPCO Research Institute, Daejeon (Korea, Republic of)

Description

In the early 1980s, many leaks in the piping systems of boiling water reactors in the USA were discovered in piping weld area which had been examined ultrasonically and found to be defect free. To enhance the reliability of ultrasonic testing system, ASME B and PV code section XI adopted the performance demonstration requirements (Appendix VIII) for the ultrasonic examination of nuclear power plant piping weld in the 1989 winter addenda for the first time. MOST Bulletin 2004-13 was published at 2004.6. Following the MEST Bulletin 2009-37 which was published at 2009.9(formerly MOST Bulletin 2004-13), all nuclear power plants in Korea shall implement performance demonstration of dissimilar metal weld. The object of this study is to develop the performance demonstration system for dissimilar metal weld ultrasonic testing of nuclear power plant in order to meet ASME Sec. XI Appendix VIII requirements and MEST Bulletin 2009-37. This paper describes the status of the development of dissimilar metal weld performance demonstration system in Korea

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2010 autumn meeting of the KNS
Dates
21-22 Oct 2010
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
42085401
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BWR TYPE REACTORS; LEAKS; PERFORMANCE; PIPES; RELIABILITY; WELDED JOINTS
Descriptors DEC
ENRICHED URANIUM REACTORS; JOINTS; POWER REACTORS; REACTORS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs, 6 figs