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Development of automatic ultrasonic testing equipment for reactor pressure vessel

Abstract

The selected weld areas of reactor pressure vessel and adjacent piping are examined by remote mechanized ultrasonic testing(MUT) equipment. Since the MUT equipment was purchased from Southwest Research Institute (SwRI) in April 1985, we have performed 15 inservice inspections and 5 preservice inspections. However, the reliability of examination was recently decreased rapidly as the problems which results from the old age of equipment and the frequent movement to plant site to site have occurred frequently. Therefore, the 3-axis control system hardware in occurring many problems among the equipments of mechanized ultrasonic testing (MUT) was designed and developed to cover the examination areas of nozzle-shell weld as specified in ASME Code Section XI and to improve the examination reliability. The new 3-axis control system hardware with the performance of this project was developed to be compatible with the old one and it was used as dual system or spare parts of the old system. Furthermore, the established technologies are expected to be applied to the similar control systems in nuclear power plant. 17 figs, 2 pix, 2 tabs, 10 refs. (Author).
Authors:
Jang, Kee Ok; Park, Dae Yung; Park, Moon Hoh; Koo, Kil Mo; Park, Kwang Heui; Kang, Sang Sin; Bang, Heui Song; Noh, Heui Choong; Kong, Woon Sik [1] 
  1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Publication Date:
Aug 01, 1994
Product Type:
Technical Report
Report Number:
KAERI-RR-1459/94
Reference Number:
SCA: 420500; 220200; PA: AIX-27:014925; EDB-96:047411; NTS-96:014099; SN: 96001546000
Resource Relation:
Other Information: PBD: Aug 1994
Subject:
42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES; 22 NUCLEAR REACTOR TECHNOLOGY; REACTOR VESSELS; ULTRASONIC TESTING; ULTRASONIC MACHINING; COMPUTERIZED CONTROL SYSTEMS; CONTAINMENT SHELLS; DATA ACQUISITION SYSTEMS; NOZZLES; PRESSURE VESSELS; WELDED JOINTS
OSTI ID:
193858
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE96614459; TRN: KR9500146014925
Availability:
INIS; OSTI as DE96614459
Submitting Site:
KRN
Size:
80 p.
Announcement Date:

Citation Formats

Jang, Kee Ok, Park, Dae Yung, Park, Moon Hoh, Koo, Kil Mo, Park, Kwang Heui, Kang, Sang Sin, Bang, Heui Song, Noh, Heui Choong, and Kong, Woon Sik. Development of automatic ultrasonic testing equipment for reactor pressure vessel. Korea, Republic of: N. p., 1994. Web.
Jang, Kee Ok, Park, Dae Yung, Park, Moon Hoh, Koo, Kil Mo, Park, Kwang Heui, Kang, Sang Sin, Bang, Heui Song, Noh, Heui Choong, & Kong, Woon Sik. Development of automatic ultrasonic testing equipment for reactor pressure vessel. Korea, Republic of.
Jang, Kee Ok, Park, Dae Yung, Park, Moon Hoh, Koo, Kil Mo, Park, Kwang Heui, Kang, Sang Sin, Bang, Heui Song, Noh, Heui Choong, and Kong, Woon Sik. 1994. "Development of automatic ultrasonic testing equipment for reactor pressure vessel." Korea, Republic of.
@misc{etde_193858,
title = {Development of automatic ultrasonic testing equipment for reactor pressure vessel}
author = {Jang, Kee Ok, Park, Dae Yung, Park, Moon Hoh, Koo, Kil Mo, Park, Kwang Heui, Kang, Sang Sin, Bang, Heui Song, Noh, Heui Choong, and Kong, Woon Sik}
abstractNote = {The selected weld areas of reactor pressure vessel and adjacent piping are examined by remote mechanized ultrasonic testing(MUT) equipment. Since the MUT equipment was purchased from Southwest Research Institute (SwRI) in April 1985, we have performed 15 inservice inspections and 5 preservice inspections. However, the reliability of examination was recently decreased rapidly as the problems which results from the old age of equipment and the frequent movement to plant site to site have occurred frequently. Therefore, the 3-axis control system hardware in occurring many problems among the equipments of mechanized ultrasonic testing (MUT) was designed and developed to cover the examination areas of nozzle-shell weld as specified in ASME Code Section XI and to improve the examination reliability. The new 3-axis control system hardware with the performance of this project was developed to be compatible with the old one and it was used as dual system or spare parts of the old system. Furthermore, the established technologies are expected to be applied to the similar control systems in nuclear power plant. 17 figs, 2 pix, 2 tabs, 10 refs. (Author).}
place = {Korea, Republic of}
year = {1994}
month = {Aug}
}