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ST 6.3 –
Protección radiológica del público y el ambiente
EXPOSURE DOSE ASSESSMENT OF DESIGN BASIS ACCIDENTS AT
NUCLEAR POWER PLANT BASED ON ICRP 103 DOSIMETRIC SETTING
Shin, Hyeong-Ki*; Lee, Byeong-soo
Korea Institute of Nuclear Safety (KINS). South Korea.
* Responsible author, email: k685ysj@kins.re.kr
In the International Commission on Radiological Protection (ICRP) 2007 recommendations,
ICRP adopted reference male and female computational phantoms (ICRP 110) for forthcoming
updates of organ dose coefficients of both internal and external radiation sources. In early stage
of nuclear power plant accident, the major exposure radiation source terms are noble gases.
For assessment of external doses due to noble gases, the dose coefficients prescribed in FRG
12 & 13 have been widely used. The objectives of this study are to calculate the effective dose
rate conversion factors, equivalent dose rate conversion factors and exposure doses of
radioactive noble gases for the cases of air submersion with the nuclear decay data (ICRP 107)
and the ICRP 103 adult reference phantoms. Effective dose rate conversion factors for most of
noble gases in this study are about 90 % to 135 % difference for FGR12 & 13 data except a few
nuclides. The assumption to compute the exposure doses, the TID-14844 radiation source
terms was used, the assessment distance from reactor core was 560m and atmospheric
dispersion factors were calculated with USNRC RG 1.145 methodology. Finally, the assessment
doses by newly made DCFs were compared to that of using previous DCFs in FGR12 & 13.