Abstract
Some components of Japan Power Demonstration Reactor (JPDR), which has been decommissioned, are utilized for the investigation of aging of a nuclear reactor at Japan Atomic Energy Research Institute (JAERI). The present paper reports the through-thickness attenuation characteristics of irradiation hardening based on the examination of the reactor pressure vessel (RPV). The RPV was exposed to the maximum dose of 2x10{sup 18} n/cm{sup 2} (E>1MeV) at the inner surface at the corebelt region. At the position of 50 mm inside the pressure vessel steel from the inner surface, dose is decreased roughly to 50%. The attenuation was evaluated either by detailed calculation or JEAC 4206 attenuation equation. Through-thickness attenuation of irradiation hardening was predicted using these dose attenuation curves, and compared with the results of hardness measurements. As a result, actual attenuation was larger than predicted values. (author).
Suzuki, Masahide;
Idei, Yoshio
[1]
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Suzuki, Masahide, and Idei, Yoshio.
Study on through-thickness attenuation of irradiation embrittlement using JPDR pressure vessel.
Japan: N. p.,
1994.
Web.
Suzuki, Masahide, & Idei, Yoshio.
Study on through-thickness attenuation of irradiation embrittlement using JPDR pressure vessel.
Japan.
Suzuki, Masahide, and Idei, Yoshio.
1994.
"Study on through-thickness attenuation of irradiation embrittlement using JPDR pressure vessel."
Japan.
@misc{etde_10121700,
title = {Study on through-thickness attenuation of irradiation embrittlement using JPDR pressure vessel}
author = {Suzuki, Masahide, and Idei, Yoshio}
abstractNote = {Some components of Japan Power Demonstration Reactor (JPDR), which has been decommissioned, are utilized for the investigation of aging of a nuclear reactor at Japan Atomic Energy Research Institute (JAERI). The present paper reports the through-thickness attenuation characteristics of irradiation hardening based on the examination of the reactor pressure vessel (RPV). The RPV was exposed to the maximum dose of 2x10{sup 18} n/cm{sup 2} (E>1MeV) at the inner surface at the corebelt region. At the position of 50 mm inside the pressure vessel steel from the inner surface, dose is decreased roughly to 50%. The attenuation was evaluated either by detailed calculation or JEAC 4206 attenuation equation. Through-thickness attenuation of irradiation hardening was predicted using these dose attenuation curves, and compared with the results of hardness measurements. As a result, actual attenuation was larger than predicted values. (author).}
place = {Japan}
year = {1994}
month = {Nov}
}
title = {Study on through-thickness attenuation of irradiation embrittlement using JPDR pressure vessel}
author = {Suzuki, Masahide, and Idei, Yoshio}
abstractNote = {Some components of Japan Power Demonstration Reactor (JPDR), which has been decommissioned, are utilized for the investigation of aging of a nuclear reactor at Japan Atomic Energy Research Institute (JAERI). The present paper reports the through-thickness attenuation characteristics of irradiation hardening based on the examination of the reactor pressure vessel (RPV). The RPV was exposed to the maximum dose of 2x10{sup 18} n/cm{sup 2} (E>1MeV) at the inner surface at the corebelt region. At the position of 50 mm inside the pressure vessel steel from the inner surface, dose is decreased roughly to 50%. The attenuation was evaluated either by detailed calculation or JEAC 4206 attenuation equation. Through-thickness attenuation of irradiation hardening was predicted using these dose attenuation curves, and compared with the results of hardness measurements. As a result, actual attenuation was larger than predicted values. (author).}
place = {Japan}
year = {1994}
month = {Nov}
}