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Verification of annual limits on intake and concentration limits for radionuclides produced in accelerator facilities

Technical Report:

Abstract

Many of the radionuclides produced by Accelerators are not compiled in ICRP Publication 30. Annual limits on intake (ALI{sub s}) of the 78 radionuclides were calculated by other authors using a Code System, PIEDEC-R. Also, they calculated the derived concentration limits on air, exhaust air and draining water etc. compatible with such derived limits in domestic regulations. Then, a proposal was made to verify their results before publication. To respond to the proposal, annual limits on intake of 12 radionuclides selected from the above 78 radionuclides were calculated by DOSDAC, the code system developed in JAERI for the assessment of dose coefficient for intake and the results were compared in the present report. In conclusion, the ratios of the calculation result of ALI{sub s} by DOSDAC to that by PIEDEC-R were within the range from -8% to +18%, and so, agreement was well provided that the data for the radionuclides are sufficiently arranged in Evaluated Nuclear Structure Data File (ENSDF). As for Ba-129, of which data are not sufficient in ENSDF, relevant nuclear data were supplemented and its ALI{sub s} were calculated. No problem was found on calculation of derived limits in the report of referred authors, and used parameters  More>>
Authors:
Suga, Shinichi; Togawa, Orihiko; Yamaguchi, Yukichi; Kawai, Katsuo; Oshino, Masao; [1]  Tamura, Tutomu
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Jul 01, 1992
Product Type:
Technical Report
Report Number:
JAERI-M-92-110
Reference Number:
SCA: 560190; PA: JPN-92:012156; SN: 93000919858
Resource Relation:
Other Information: PBD: Jul 1992
Subject:
61 RADIATION PROTECTION AND DOSIMETRY; ACCELERATOR FACILITIES; ANNUAL LIMIT OF INTAKE; ICRP; RADIATION DOSES; D CODES; BARIUM 129; ISOTOPE PRODUCTION; INHALATION; YTTRIUM 85; RUTHENIUM 95; RHODIUM 106; CADMIUM 105; INDIUM 108; 560190; RADIATION PROTECTION STANDARDS
OSTI ID:
10112577
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE93754291; TRN: JP9212156
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
81 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Suga, Shinichi, Togawa, Orihiko, Yamaguchi, Yukichi, Kawai, Katsuo, Oshino, Masao, and Tamura, Tutomu. Verification of annual limits on intake and concentration limits for radionuclides produced in accelerator facilities. Japan: N. p., 1992. Web.
Suga, Shinichi, Togawa, Orihiko, Yamaguchi, Yukichi, Kawai, Katsuo, Oshino, Masao, & Tamura, Tutomu. Verification of annual limits on intake and concentration limits for radionuclides produced in accelerator facilities. Japan.
Suga, Shinichi, Togawa, Orihiko, Yamaguchi, Yukichi, Kawai, Katsuo, Oshino, Masao, and Tamura, Tutomu. 1992. "Verification of annual limits on intake and concentration limits for radionuclides produced in accelerator facilities." Japan.
@misc{etde_10112577,
title = {Verification of annual limits on intake and concentration limits for radionuclides produced in accelerator facilities}
author = {Suga, Shinichi, Togawa, Orihiko, Yamaguchi, Yukichi, Kawai, Katsuo, Oshino, Masao, and Tamura, Tutomu}
abstractNote = {Many of the radionuclides produced by Accelerators are not compiled in ICRP Publication 30. Annual limits on intake (ALI{sub s}) of the 78 radionuclides were calculated by other authors using a Code System, PIEDEC-R. Also, they calculated the derived concentration limits on air, exhaust air and draining water etc. compatible with such derived limits in domestic regulations. Then, a proposal was made to verify their results before publication. To respond to the proposal, annual limits on intake of 12 radionuclides selected from the above 78 radionuclides were calculated by DOSDAC, the code system developed in JAERI for the assessment of dose coefficient for intake and the results were compared in the present report. In conclusion, the ratios of the calculation result of ALI{sub s} by DOSDAC to that by PIEDEC-R were within the range from -8% to +18%, and so, agreement was well provided that the data for the radionuclides are sufficiently arranged in Evaluated Nuclear Structure Data File (ENSDF). As for Ba-129, of which data are not sufficient in ENSDF, relevant nuclear data were supplemented and its ALI{sub s} were calculated. No problem was found on calculation of derived limits in the report of referred authors, and used parameters and treatment of fractions were considered adequate. (author).}
place = {Japan}
year = {1992}
month = {Jul}
}