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Yoshizawa, Michio
Nihon Genshiryoku Gakkai-Shi ATOMO
, 64(8), p.439 - 441, 2022/08
no abstracts in English
Kumazawa, Shigeru
Proceedings of 10th International Congress of the International Radiation Protection Association (IRPA-10) (CD-ROM), 12 Pages, 2000/05
no abstracts in English
Mizushita, Seiichi
Proc. of 20th JAIF-KAIF Seminar on Nuclear Industry, p.4.1.1 - 4.1.15, 1998/00
no abstracts in English
; Kawai, Katsuo
Radiation and Society:Comprehending Radiation Risk, 2(0), p.76 - 82, 1994/10
no abstracts in English
Kawai, Katsuo; ; ; ;
Hoken Butsuri, 28, p.203 - 209, 1993/00
no abstracts in English
Takahashi, Fumiaki; Manabe, Kentaro; Sato, Kaoru
no journal, ,
Safety standards for radiation are based on concepts of the 1990 Recommendations by the International Commission on Radiological Protection (ICRP) in Japan. ICRP has released the 2007 Recommendations that replace the 1990 Recommendations and then discussions have been made to revise the safety standards for radiation in Japan. Thus, we investigate Occupational Intakes of Radionuclides (OIR) by ICRP to clarify issues that should be considered for revisions on limitations for internal exposure. ICRP has continuously adopted internal exposure dosimetry by using effective dose coefficients with the unit of Sv/Bq. However, effective dose coefficients are not presented for radioisotopes whose half-lives are less than 10 minutes, in OIR. Exposure conditions should be discussed in regulating submersion exposure, in addition to radioisotopes.
Manabe, Kentaro
no journal, ,
The dose coefficients, which are committed effective doses per unit intake of radionuclides, used for assessment of internal exposure doses. The current coefficients used in statutory procedure are based on the 1990 Recommendations of the International Commission on Radiological Protection (ICRP). On the other hand, the ICRP has been developing and providing dose coefficients based on the 2007 Recommendations, which supersedes the 1990 Recommendations. The development of dose coefficients for occupational intakes has been completed in April 2022. In this presentation, the models and data used in the development of the new coefficients will be explained and the differences between the old and new ones will be introduced.
Manabe, Kentaro
no journal, ,
JAEA has been developing the Internal Dose Calculation Code, IDCC, as a technical basis for incorporating the 2007 Recommendations of the International Commission on Radiological Protection (ICRP) into the Japanese regulatory standards for protection against internal exposure. Currently, all of the systemic kinetic models and radiation absorption fraction data are introduced to IDCC to perform the internal dose assessment for occupational exposure. In this presentation, we will report on the backgrounds, current status, and future plans of IDCC development, and raise the issue of the need for standard models for retrospective dose assessment in the event of a radiation accident.
