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Development of inspection safety evaluation technology

Abstract

The purpose of this project is to protection nation inspector`s over exposure from radiation that can be occurred by inspection activity at nuclear facilities and its environment, and to ensure the safety of inspection activity at the nuclear facilities. To effectively carry out the domestic inspection task to be enforced from 1996, the evaluation for special radiation exposure rate of nuclear facilities, air and surface contamination level, and measurement and monitoring of water contamination level were made to determine whether these measured values exceeded permissible limitations, and to protect the inspector`s over exposure from radiation at domestic nuclear facilities. Management of inspector`s exposure was carried out under assistance of the Department of Health Physics. Performance tests of two gamma detectors, one neutron detector, alpha and beta detector, and gamma spectroscopy analyzer were carried out to control dose on extremity, the characteristic test for extremity dosimeter was carried out and the theoretical calculation of gamma dose conversion factors based on ANSI N13.32 standard was performed. Under the 93+2 program, IAEA began to recognize the necessity of environmental observation technology development of air-borne particulates travelled from long distance location. Associated with the necessity of this technology development, a proposal of international joint  More>>
Publication Date:
Dec 01, 1995
Product Type:
Technical Report
Report Number:
KAERI/MR-272/96
Reference Number:
SCA: 055001; PA: AIX-28:065340; EDB-97:124256; SN: 97001855691
Resource Relation:
Other Information: PBD: Dec 1995
Subject:
05 NUCLEAR FUELS; RADIATION PROTECTION; EXPOSURE RATEMETERS; INDOOR AIR CONTAMINATION; INSPECTION; NUCLEAR FACILITIES; PERSONNEL DOSIMETRY; RADIATION MONITORING; SAFEGUARDS; SAFETY; SURFACE CONTAMINATION
OSTI ID:
529190
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE98601121; TRN: KR9700059065340
Availability:
INIS; OSTI as DE98601121
Submitting Site:
KRN
Size:
148 p.
Announcement Date:
Oct 15, 1997

Citation Formats

Yoon, Seok Chul, Yoon, Yeo Chang, Kim, Jong Soo, Lee, Tae Young, Kim, Chang Ryol, Lee, Hyung Sub, and Kim, Jong Soo. Development of inspection safety evaluation technology. Korea, Republic of: N. p., 1995. Web.
Yoon, Seok Chul, Yoon, Yeo Chang, Kim, Jong Soo, Lee, Tae Young, Kim, Chang Ryol, Lee, Hyung Sub, & Kim, Jong Soo. Development of inspection safety evaluation technology. Korea, Republic of.
Yoon, Seok Chul, Yoon, Yeo Chang, Kim, Jong Soo, Lee, Tae Young, Kim, Chang Ryol, Lee, Hyung Sub, and Kim, Jong Soo. 1995. "Development of inspection safety evaluation technology." Korea, Republic of.
@misc{etde_529190,
title = {Development of inspection safety evaluation technology}
author = {Yoon, Seok Chul, Yoon, Yeo Chang, Kim, Jong Soo, Lee, Tae Young, Kim, Chang Ryol, Lee, Hyung Sub, and Kim, Jong Soo}
abstractNote = {The purpose of this project is to protection nation inspector`s over exposure from radiation that can be occurred by inspection activity at nuclear facilities and its environment, and to ensure the safety of inspection activity at the nuclear facilities. To effectively carry out the domestic inspection task to be enforced from 1996, the evaluation for special radiation exposure rate of nuclear facilities, air and surface contamination level, and measurement and monitoring of water contamination level were made to determine whether these measured values exceeded permissible limitations, and to protect the inspector`s over exposure from radiation at domestic nuclear facilities. Management of inspector`s exposure was carried out under assistance of the Department of Health Physics. Performance tests of two gamma detectors, one neutron detector, alpha and beta detector, and gamma spectroscopy analyzer were carried out to control dose on extremity, the characteristic test for extremity dosimeter was carried out and the theoretical calculation of gamma dose conversion factors based on ANSI N13.32 standard was performed. Under the 93+2 program, IAEA began to recognize the necessity of environmental observation technology development of air-borne particulates travelled from long distance location. Associated with the necessity of this technology development, a proposal of international joint research for development of the special radiation measurement and analysis has been prepared. (author). 21 tabs., 24 figs., 20 refs.}
place = {Korea, Republic of}
year = {1995}
month = {Dec}
}