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Material performance evaluation -Development of the advanced nuclear materials-

Technical Report:

Abstract

A multifrequency ACPD system was assembled. A SSRT equipment for stress corrosion cracking test was installed. A 25-ton capacity fatigue test machine was purchased as a first step to assemble a corrosion fatigue test facility. A test loop was designed to simulate the primary water chemistry condition. An Ag/AgCl external reference electrode which can be used at a temperature as high as 280 deg C was fabricated. A high temperature pH electrode was designed for fabrication. A creep test machine was designed conceptually for testing creep behaviors of Zr alloys. Preliminary design requirements were made for the instrumented capsule and a plan was made for using the uninstrumented capsule, as parts of activities to complete an integrated plan of in-reactor materials irradiation test. CHEC computer code which helped improving maintenance program against erosion/corrosion of secondary pipings of nuclear power plants was purchased. Erosion/corrosion of feedwater heater drain line of Kori Unit One was analyzed using the CHEC code as a sample calculation. (Author).
Authors:
Kim, Uh Chul; Yang, Kyung Rin; Nho, Kye Ho; Chung, Han Sub; Kim, Hong Pyo; Hwang, Sung Sik; Han, Jeong Ho; Lee, Eun Hee; Lee, Deok Hyun; Hur, Do Haeng [1] 
  1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Publication Date:
Jul 01, 1994
Product Type:
Technical Report
Report Number:
KAERI/RR-1336/93
Reference Number:
SCA: 420500; PA: AIX-26:011114; EDB-95:030715; SN: 95001324036
Resource Relation:
Other Information: PBD: Jul 1994
Subject:
42 ENGINEERING; NUCLEAR POWER PLANTS; MATERIALS TESTING; CORROSION; CORROSION FATIGUE; CRACKING; CREEP; DEFORMATION; EROSION; 420500
OSTI ID:
10111488
Research Organizations:
Korea Cancer Center Hospital, Seoul (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE95612784; TRN: KR9400173011114
Availability:
OSTI; NTIS; INIS
Submitting Site:
KRN
Size:
213 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Kim, Uh Chul, Yang, Kyung Rin, Nho, Kye Ho, Chung, Han Sub, Kim, Hong Pyo, Hwang, Sung Sik, Han, Jeong Ho, Lee, Eun Hee, Lee, Deok Hyun, and Hur, Do Haeng. Material performance evaluation -Development of the advanced nuclear materials-. Korea, Republic of: N. p., 1994. Web.
Kim, Uh Chul, Yang, Kyung Rin, Nho, Kye Ho, Chung, Han Sub, Kim, Hong Pyo, Hwang, Sung Sik, Han, Jeong Ho, Lee, Eun Hee, Lee, Deok Hyun, & Hur, Do Haeng. Material performance evaluation -Development of the advanced nuclear materials-. Korea, Republic of.
Kim, Uh Chul, Yang, Kyung Rin, Nho, Kye Ho, Chung, Han Sub, Kim, Hong Pyo, Hwang, Sung Sik, Han, Jeong Ho, Lee, Eun Hee, Lee, Deok Hyun, and Hur, Do Haeng. 1994. "Material performance evaluation -Development of the advanced nuclear materials-." Korea, Republic of.
@misc{etde_10111488,
title = {Material performance evaluation -Development of the advanced nuclear materials-}
author = {Kim, Uh Chul, Yang, Kyung Rin, Nho, Kye Ho, Chung, Han Sub, Kim, Hong Pyo, Hwang, Sung Sik, Han, Jeong Ho, Lee, Eun Hee, Lee, Deok Hyun, and Hur, Do Haeng}
abstractNote = {A multifrequency ACPD system was assembled. A SSRT equipment for stress corrosion cracking test was installed. A 25-ton capacity fatigue test machine was purchased as a first step to assemble a corrosion fatigue test facility. A test loop was designed to simulate the primary water chemistry condition. An Ag/AgCl external reference electrode which can be used at a temperature as high as 280 deg C was fabricated. A high temperature pH electrode was designed for fabrication. A creep test machine was designed conceptually for testing creep behaviors of Zr alloys. Preliminary design requirements were made for the instrumented capsule and a plan was made for using the uninstrumented capsule, as parts of activities to complete an integrated plan of in-reactor materials irradiation test. CHEC computer code which helped improving maintenance program against erosion/corrosion of secondary pipings of nuclear power plants was purchased. Erosion/corrosion of feedwater heater drain line of Kori Unit One was analyzed using the CHEC code as a sample calculation. (Author).}
place = {Korea, Republic of}
year = {1994}
month = {Jul}
}