Published May 2009 | Version v1
Miscellaneous

Causes of PWSCC in a Alloy 600 Nozzle of a PWR

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

Description

Primary water stress corrosion (PWSCC) of alloy 600 in a PWR has been an important concern. This PWSCC has been reported in the control rod drive mechanism (CRDM), the pressurizer instrumentation nozzle, and the pressurizer heater sleeve. Since the first report of a PWSCC in a steam generator (SG) drain nozzle at the Shearon Harris plant in 1988, more cases have been reported around the world. Recently, two cases of a boric acid precipitation were reported on the bottom head surface of a SG in Korea. Cracking was only found in the cold leg drain nozzles made of alloy 600 in two units. The hot leg side nozzles are corrosion resistant alloy 690. The objective of the present work is to evaluate the crack morphology of a degraded nozzle, and to seek the causes of the cracking

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

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

Conference

Title
2009 spring meeting of the KNS
Dates
18-23 May 2009
Place
Jeju (Korea, Republic of)

Optional Information

Notes
3 refs, 5 figs