• Journal of Radiation Protection and Research
• /
• v.19 no.3
• /
• pp.209-221
• /
• 1994

In the case of a severe accident of a nuclear power plant, the whole body dose and the relative importance of the radionuclides during the lifetime of an exposed person were estimated for each exposure pathway with distances from the release point. The external exposure pathways due to immersion of radioactive cloud and deposition of radioactive materials on the ground, and the internal exposure pathways due to inhalation and ingestion of contaminated foodstuffs were considered. The effects due to the ingestion of contaminated foodstuffs were estimated considering the variation of radioactive concentration in the foodstuffs according to deposition time and elapsed time after deposition using a dynamic ingestion pathway model applicable to Korean environment, named 'KORFOOD'. As the results up to 80 km from the release point, the effects due to ingestion of contaminated foodstuffs showed the highest contribution to total exposure dose. The contribution of I isotopes was the highest in the case of the external dose due to immersion of radioactive cloud and internal dose due to inhalation. The contribution of Cs isotopes was highest in the case of the external dose due to deposition of radioactive materials on the ground. In the case of the internal dose due to ingestion of contaminated foodstuffs, Cs deposition in summer and Sr deposition in winter, respectively, were the most dominant radionuclide to whole body.

• Journal of Radiation Protection and Research
• /
• v.23 no.4
• /
• pp.211-218
• /
• 1998

The distributional effects of radioactive materials on external gamma exposure have been analyzed. An approximate method for estimating external gamma dose given from an arbitrary distribution of radioactive material has been developed. The minimum gamma exposure given from a point source is shown at 0.07 MeV if the source to receptor distance is shorter than 10 m. But if the receptor to point source distance is longer than 20 m, gamma exposure rate increases monotonously according to the average gamma energy. For the analysis of the effects of volume source, we estimated the gamma dose given from different size of hemisphere in which radioactive materials are distributed uniformly. When the radius of hemisphere is longer than 40 m, external gamma dose rate increases monotonously. The gamma dose rate given from the radioactive materials deposited on the ground shows the minimum value at 0.07 MeV in any case. The analysis shows that external gamma exposure is strongly dependent on the distribution of radioactive materials in the environment and gamma energy.

• 대한방사선방어학회:학술대회논문집
• /
• 2010.04a
• /
• pp.230-231
• /
• 2010

• Radioisotope journal
• /
• v.10 no.3
• /
• pp.84-86
• /
• 1995

• Radioisotope journal
• /
• v.16 no.1
• /
• pp.107-119
• /
• 2001

• Radioisotope journal
• /
• v.12 no.1
• /
• pp.68-72
• /
• 1997

• Radioisotope journal
• /
• v.9 no.1
• /
• pp.58-64
• /
• 1994

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2004.06a
• /
• pp.130-130
• /
• 2004

본 연구는 연구로 1,2호기 해체과정에서 발생되는 자체처분대상 콘크리트폐기물을 재활용하기 위해서 NUREG-1640 에서 제시하고 있는 시나리오에 대하여 외부피폭선량을 평가하였다. NUREG-1640에서는 콘크리트폐기물 재활용에 적용시 7가지 시나리오를 제시하고 있으며, 각 시나리오를 살펴보면 대량의 콘크리트에 인접, 콘크리트폐기물 수송, 콘크리트폐기물 처리, 매립을 위한 처분활동, 매립지 폐쇄 후 거주자, 콘크리트폐기물 이용 도로건설, 도로포장재로 대량의 콘크리트 이용이 있다.(중략)

• Journal of Radiation Protection and Research
• /
• v.11 no.2
• /
• pp.152-161
• /
• 1986

외부방사선피폭(外部放射線被曝)으로 인한 위험(危險)의 평가(評價)와 관련된 량(量) 및 개념(槪念)의 동향(動向)과 미해결(未解決)된 문제점(問題點)들에 대하여 살펴보았다. 특히 ICRU 39의 실용량(實用量)에 근거(根據)한 선량환산인자(線量換算因子), 선질계수(線質係數)의 재정의(再定義), 성별(性別)에 따른 위험(危險)의 차이(差異) 그리고 기타조직(其他組織)의 선정문제등(選定問題等)에 대하여 구체적(具體的)으로 논(論)하였다.

• Journal of radiological science and technology
• /
• v.35 no.2
• /
• pp.141-149
• /
• 2012

The aims of this study are to assess external radiation exposed doses of body and hands of nuclear medicine workers who handle radiation sources, and to measure radiation exposed doses of the hands induced by a whole body bone scan with high frequency and handling a radioactive sources like $^{99m}Tc$-HDP and $^{18}F$-FDG in the PET/CT examination. Skillful workers, who directly dispense and inject from radiation sources, were asked to wear a TLD on the chest and ring finger. Then, radiation exposed dose and duration exposed from daily radiation sources for each section were measured by using a pocket dosimeter for the accumulated external doses and the absorbed dose to the hands. In the survey of four medical institutions in Incheon Metropolitan City, only one of four institutions has a radiation dosimeter for local area like hands. Most of institutions uses radiation shielding devices for the purpose of protecting the body trunk, not local area. Even some institutions were revealed not to use such a shielding device. The exposed doses on the hands of nuclear medicine workers who directly handles radioactive sources were approximately twice as much as those on the body. The radiation exposure level for each section of the whole body bone scan with high frequency and that of the PET/CT examination showed that radiation doses were revealed in decreasing order of synthesis of radioactive medicine and installation to a dispensing container, dispensing, administering and transferring. Furthermore, there were statistically significant differences of radiation exposure doses of the hands before and after wearing a syringe shielder in administration of a radioactive sources. In this study, although it did not reach the permissible effective dose for nuclear medicine, the occupational workers were exposed by relatively higher dose level than the non-occupational workers. Therefore, the workers, who closely exposed to radioactive sources should be in compliance with safety management regulations, and take actions to maximally reduce locally exposed dose to hands monitoring with ring TLD.