• Title/Summary/Keyword: 기준방사선장

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Calculation of Route Doses for Korean-based International Airline Routes using CARI-6 and Estimation of Aircrew Exposure (CARI-6를 이용한 국제선 노선별 선량 및 항공승무원의 피폭선량 평가)

  • Hong, J.H.;Kwon, J.W.;Jung, J.H.;Lee, J.K.
    • Journal of Radiation Protection and Research
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    • v.29 no.2
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    • pp.141-150
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    • 2004
  • Dose rate characteristics of cosmic radiation field at flight altitudes were analyzed and the route doses to the personnels on board due to cosmic-ray were calculated for Korean-based commercial international airline routes using CARI-6. Annual individual doses to aircrew and the collective effective dose of passengers were estimated by applying the calculated route doses to the flight schedules of aircrew and the air travel statistics of Korea. The result shows that the annual doses to aircrew, around 2.62 mSv, exceed the annual dose limit of public and are comparable to doses of the group of workers occupationally exposed. Therefore it is necessary to consider the frequent flyers as well as the aircrew as the occupational exposure group. The annual collective dose to 11 million Korean passengers in 2001 appeared to be 136 man-Sv. The results should be modified when the dose rates of cosmic radiation at high altitude are revised by taking into account the changes in the radiation weighting factors for protons and neutrons as given in ICRP 92.

Intercomparison Study of the Neutron Personnel Dosemeters (중성자 개인선량계 상호비교)

  • Kim, Bong-Hwan;Kim, Jang-Lyul;Chang, Si-Young
    • Journal of Radiation Protection and Research
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    • v.23 no.1
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    • pp.49-57
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    • 1998
  • Domestic intercomparison study of the neutron personnel dosemeters was performed for the first time in Korea. Thirteen types of neutron dosemeters from twelve institutions took part in this intercomparison study and the $D_2O$ moderated Cf-252 source of KAERI was used for irradiation. Eight of the fifteen dosemeters submitted by each participant were divided into two groups and each group was irradiated with different doses of the simulated mixed fields of neutron and gamma. The participants assessed their dosemeter reading in terms of the personal dose equivalent, Hp(10), for both neutron and gamma dose. The ratio of the reported dose equivalent to the delivered dose equivalent for comparison between participants ranged from 0.55 to 1.34 for neutron, from 0.54 to 1.32 for gamma and from 0.75 to 1.20 for total dose. This intercomparison results show that all dosemeter processors, especially for neutron category, are able to pass the personnel dosemeter performance test which shall be enforced according to the ordinance of the MOST, No. 96-6.

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