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A preliminary study for the life extension of nuclear power plants

Technical Report:

Abstract

Steam generator tubings of a nuclear power plant are very thin to have efficient heat exchange. Steam generator tubings have experienced various types of corrosion damages under the sludge pile and in the tube-tube sheet crevice during operation at high temperature and high pressure. Types of degradation of steam generator tubings found in domestic nuclear power plants are pitting, secondary side stress corrosion cracking caused by Pb, primary water SCC, and fretting in the area in contact with antivibration bar. The ACPD (Alternate Current Potential Drop), which can detect the initiation and propagation of the microcracks, was assembled. The C-ring specimens were machined in order to test a stress corrosion cracking in Pb containing aqueous solution. The denting (stress increasing factor) test on the carbon steel was conducted, and pitting resistance of the different alloy was evaluated. As a result of the chemical cleaning process, it is concluded that the high temperature (125 deg C) chemical cleaning process could be applicable. And it was investigated that there were many cases of cracking of high strength materials used in the reactor internals throughout world. There was a failure in Korea also. (Author).
Authors:
Kim, Uh Chul; Chung, Han Sub; Kim, Hong Pyo; Lee, Eun Hee; Hwang, Seong Sik; Hur, Do Haeng [1] 
  1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Publication Date:
Dec 01, 1993
Product Type:
Technical Report
Report Number:
KAERI/RR-1293/93
Reference Number:
SCA: 220200; PA: AIX-26:011142; EDB-95:028349; SN: 95001324051
Resource Relation:
Other Information: PBD: Dec 1993
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; NUCLEAR POWER PLANTS; MAINTENANCE; CLEANING; CORROSION DENTING; ELECTROCHEMICAL CORROSION; FRETTING CORROSION; PITTING CORROSION; SLUDGES; STEAM GENERATORS; 220200; COMPONENTS AND ACCESSORIES
OSTI ID:
10111510
Research Organizations:
Korea Cancer Center Hospital, Seoul (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE95612799; TRN: KR9400139011142
Availability:
OSTI; NTIS; INIS
Submitting Site:
KRN
Size:
110 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Kim, Uh Chul, Chung, Han Sub, Kim, Hong Pyo, Lee, Eun Hee, Hwang, Seong Sik, and Hur, Do Haeng. A preliminary study for the life extension of nuclear power plants. Korea, Republic of: N. p., 1993. Web.
Kim, Uh Chul, Chung, Han Sub, Kim, Hong Pyo, Lee, Eun Hee, Hwang, Seong Sik, & Hur, Do Haeng. A preliminary study for the life extension of nuclear power plants. Korea, Republic of.
Kim, Uh Chul, Chung, Han Sub, Kim, Hong Pyo, Lee, Eun Hee, Hwang, Seong Sik, and Hur, Do Haeng. 1993. "A preliminary study for the life extension of nuclear power plants." Korea, Republic of.
@misc{etde_10111510,
title = {A preliminary study for the life extension of nuclear power plants}
author = {Kim, Uh Chul, Chung, Han Sub, Kim, Hong Pyo, Lee, Eun Hee, Hwang, Seong Sik, and Hur, Do Haeng}
abstractNote = {Steam generator tubings of a nuclear power plant are very thin to have efficient heat exchange. Steam generator tubings have experienced various types of corrosion damages under the sludge pile and in the tube-tube sheet crevice during operation at high temperature and high pressure. Types of degradation of steam generator tubings found in domestic nuclear power plants are pitting, secondary side stress corrosion cracking caused by Pb, primary water SCC, and fretting in the area in contact with antivibration bar. The ACPD (Alternate Current Potential Drop), which can detect the initiation and propagation of the microcracks, was assembled. The C-ring specimens were machined in order to test a stress corrosion cracking in Pb containing aqueous solution. The denting (stress increasing factor) test on the carbon steel was conducted, and pitting resistance of the different alloy was evaluated. As a result of the chemical cleaning process, it is concluded that the high temperature (125 deg C) chemical cleaning process could be applicable. And it was investigated that there were many cases of cracking of high strength materials used in the reactor internals throughout world. There was a failure in Korea also. (Author).}
place = {Korea, Republic of}
year = {1993}
month = {Dec}
}