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Development of radiation protection and measurement technology -A study on the radiation and environmental safety-

Technical Report:

Abstract

Reference radiation fields which can meet the national and international standard and criteria such as the ANSI N13.11 have been designed, produced and evaluated to maintain the national traceability and reliability of the radiation measurement and to provide precise calibration of the various radiation measuring instruments as well as standard irradiation of the personal dosimeters for the performance evaluation. Existing dose calculation algorithm has been improved to correctly evaluate the shallow dose from the {beta}(Ti-204) + {gamma}(Cs-137) mixed radiation exposure by applying the TLD response correction function newly derived in this study. A mathematical algorithm to calculate the internal dose from inhalation of the uranium isotopes has been developed on the basis of the ICRP-30 respiratory tract model. Detailed performance analysis of the KAERI lung counter has been carried out to participate in the intercomparison of lung dosimetry. A preliminary and basic study on the quantitative method of optimal dose reduction based on the ALARA concept has been performed to technically support and strengthen the national radiation protection infrastructure. (Author).
Authors:
Publication Date:
Jul 01, 1994
Product Type:
Technical Report
Report Number:
KAERI/RR-1328/93
Reference Number:
SCA: 560180; 560101; PA: AIX-26:010535; EDB-95:031805; SN: 95001323799
Resource Relation:
Other Information: PBD: Jul 1994
Subject:
61 RADIATION PROTECTION AND DOSIMETRY; RADIATION PROTECTION; DOSIMETRY; ALARA; BETA DETECTION; GAMMA RADIATION; NEUTRON FLUX; PERSONNEL DOSIMETRY; X RADIATION; 560180; 560101; RADIATION PROTECTION PROCEDURES; DOSIMETRY AND MONITORING
OSTI ID:
10111364
Research Organizations:
Korea Cancer Center Hospital, Seoul (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE95612559; TRN: KR9400166010535
Availability:
OSTI; NTIS; INIS
Submitting Site:
KRN
Size:
219 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Chang, Si Young, Seo, Kyeong Won, Yoon, Seok Cheol, Lee, Tae Yeong, Kim, Bong Hwan, Chung, Deok Yeon, Lee, Ki Chang, Kim, Jong Soo, Yoon, Yeo Chang, Kim, Jang Ryeol, and Lee, Sang Yoon. Development of radiation protection and measurement technology -A study on the radiation and environmental safety-. Korea, Republic of: N. p., 1994. Web.
Chang, Si Young, Seo, Kyeong Won, Yoon, Seok Cheol, Lee, Tae Yeong, Kim, Bong Hwan, Chung, Deok Yeon, Lee, Ki Chang, Kim, Jong Soo, Yoon, Yeo Chang, Kim, Jang Ryeol, & Lee, Sang Yoon. Development of radiation protection and measurement technology -A study on the radiation and environmental safety-. Korea, Republic of.
Chang, Si Young, Seo, Kyeong Won, Yoon, Seok Cheol, Lee, Tae Yeong, Kim, Bong Hwan, Chung, Deok Yeon, Lee, Ki Chang, Kim, Jong Soo, Yoon, Yeo Chang, Kim, Jang Ryeol, and Lee, Sang Yoon. 1994. "Development of radiation protection and measurement technology -A study on the radiation and environmental safety-." Korea, Republic of.
@misc{etde_10111364,
title = {Development of radiation protection and measurement technology -A study on the radiation and environmental safety-}
author = {Chang, Si Young, Seo, Kyeong Won, Yoon, Seok Cheol, Lee, Tae Yeong, Kim, Bong Hwan, Chung, Deok Yeon, Lee, Ki Chang, Kim, Jong Soo, Yoon, Yeo Chang, Kim, Jang Ryeol, and Lee, Sang Yoon}
abstractNote = {Reference radiation fields which can meet the national and international standard and criteria such as the ANSI N13.11 have been designed, produced and evaluated to maintain the national traceability and reliability of the radiation measurement and to provide precise calibration of the various radiation measuring instruments as well as standard irradiation of the personal dosimeters for the performance evaluation. Existing dose calculation algorithm has been improved to correctly evaluate the shallow dose from the {beta}(Ti-204) + {gamma}(Cs-137) mixed radiation exposure by applying the TLD response correction function newly derived in this study. A mathematical algorithm to calculate the internal dose from inhalation of the uranium isotopes has been developed on the basis of the ICRP-30 respiratory tract model. Detailed performance analysis of the KAERI lung counter has been carried out to participate in the intercomparison of lung dosimetry. A preliminary and basic study on the quantitative method of optimal dose reduction based on the ALARA concept has been performed to technically support and strengthen the national radiation protection infrastructure. (Author).}
place = {Korea, Republic of}
year = {1994}
month = {Jul}
}