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Hirouchi, Jun; Tokashiki, Yuji*; Takahara, Shogo; Manabe, Kentaro
JAEA-Research 2021-001, 284 Pages, 2021/03
JAEA-Research-2021-001.pdf:4.23MB
Doses to the public are calculated with internal dose coefficients based on the publications of the International Commission on Radiological Protection (ICRP) in OSCAAR, which is a level 3 Probabilistic Risk Assessment code developed by Japan Atomic Energy Agency (JAEA). The gastrointestinal absorption fraction, 
, which is one of parameters of internal dose coefficient, is given the recommended value. However, although it has been reported that has uncertainty, the uncertainty analysis of has been performed on few radionuclides. In this report, to evaluate the influence of uncertainty of on the internal dose, we calculated the internal dose coefficient with various , and derive the relationship between the coefficient and . As a result, we indicate that the relationships are expressed by a linear function for radionuclides with a half-life of more than 0.5 days and are expressed by a cubic function for radionuclides with a half-life of less than 0.5 days.
Takahashi, Fumiaki; Manabe, Kentaro; Sato, Kaoru; Tokashiki, Yuji*
no journal, ,
If national radiation safety regulations are revised by adapting the concept of the ICRP 2007 Recommendations, the protection standard values are also reviewed for radiation exposure. Thus, JAEA has developed an internal dosimetry code based on the ICRP 2007 Recommendations since FY 2017. Two functions are to be incorporated to the codes. One is "dose coefficient calculation function" that is used to verify the new dose coefficients by ICRP and the other is "nuclide intake estimation function" for internal dosimetry monitoring. In addition, we have developed GUI to set up calculation condition and functions to indicate results. In the dose coefficient calculation function, a user can set up internal dosimetry model based upon the 1990 recommendation to investigate the influencing factors on a difference between the old and new dose coefficients. In addition, results such as in-vivo radioactivity are also displayed with a graph in the nuclide intake estimation function. We will report an overview of the beta version of the code that integrates the two functions.
Manabe, Kentaro; Tokashiki, Yuji*; Sato, Kaoru; Takahashi, Fumiaki
no journal, ,
Nuclear Safety Research Center of Japan Atomic Energy Agency has been processing a 4-year research project from FY2017 to FY2020 to develop a computation code for internal dosimetry based upon the ICRP 2007 Recommendations contracted from Nuclear Regulation Authority of Japan. A beta ware of the code was completed by developing a graphical user interface to set calculation conditions with combining the two functions: dose coefficients calculation function and intake estimation function in this fiscal year which is the 3rd year of this project. We will report the summary of the beta ware and the future plan to finish the development project and to make the code open to the public.