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).
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]
- Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
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}
}
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}
}