• 동위원소뉴스
• /
• no.6 s.6
• /
• pp.1-1
• /
• 1997

• 동위원소뉴스
• /
• no.8 s.44
• /
• pp.2-5
• /
• 2000

• 동위원소뉴스
• /
• no.7 s.43
• /
• pp.2-4
• /
• 2000

• 동위원소뉴스
• /
• no.3 s.99
• /
• pp.5-5
• /
• 2005

• The Korean Journal of Nuclear Medicine Technology
• /
• v.14 no.2
• /
• pp.26-32
• /
• 2010

Purpose: It is to find the way to minimize occupationally exposed dose for workers in vivo tests in each working stage within the range of the working environment which does not ruin the examination and the performance efficiency. Materials and Methods: The process of the nuclear tests in vivo using a radioactive isotope consists of radioisotope distribution, a radioisotope injection ($^{99m}Tc$, $^{18}F$-FDG), and scanning and guiding patients. Using a measuring instrument of RadEye-G10 gamma survey meter (Thermo SCIENTIFIC), the exposure doses in each working stage are measured and evaluated. Before the radioisotope injection the patients are explained about the examination and educated about matters that require attention. It is to reduce the meeting time with the patients. In addition, workers are also educated about the outside exposure and have to put on the protected devices. When the radioisotope is injected to the patients the exposure doses are measured due to whether they are in the protected devices or not. It is also measured due to whether there are the explanation about the examination and the education about matters that require attention or not. The total exposure dose is visualized into the graph in using Microsoft office excel 2007. The difference of this doses are analyzed by wilcoxon signed ranks test in using SPSS (statistical package for the social science) program 12.0. In this case of p<0.01, this study is reliable in the statistics. Results: It was reliable in the statistics that the exposure dose of injecting $^{99m}Tc$-DPD 20 mCi in wearing the protected devices showed 88% smaller than the dose of injecting it without the protected devices. However, it was not reliable in the statistics that the exposure dose of injecting $^{18}F$-FDG 10 mCi with wearing protected devices had 26% decrease than without them. Training before injecting $^{99m}Tc$-DPD 20 mCi to patient made the exposure dose drop to 63% comparing with training after the injection. The dose of training before injecting $^{18}F$-FDG 10 mCi had 52% less then the training after the injection. Both of them were reliable in the statistics. Conclusion: In the examination of using the radioisotope $^{99m}Tc$, wearing the protected devices are more effective to reduce the exposure dose than without wearing them. In the case of using $^{18}F$-FDG, reducing meeting time with patients is more effective to drop the exposure dose. Therefore if we try to protect workers from radioactivity according to each radioisotope characteristic it could be more effective and active radiation shield from radioactivity.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2003.11a
• /
• pp.290-299
• /
• 2003

고준위 방사성 폐기물 처분장으로부터 유출된 핵종이 인간 생태계에 도달하여 어느 정도의 선량률로서 피폭을 일으키는가를 보이기 위한 생태계 피폭 모델링 및 평가 연구는 처분안전성 평가의 최종 단계로서 핵종 유출의 결과가 인간에게 어느 정도의 방사선 피폭을 주는가를 보이는 것이 그 주요한 내용이 된다. 이 연구를 통하여 도출된 시나리오 중에서 가장 기본이 될 수 있는 생태계에 대하여 AMBER를 사용하여 피폭 계산을 수행하여 선량 환산 인자 평가를 계산해 보았다. AMBER 코드는 핵종 이동 계산을 위해 여러 개의 구획을 설정하고 구획간의 핵종 이동은 핵종 전이 계수(mass transfer coefficient)를 이용하여 계산한다.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2003.11a
• /
• pp.579-583
• /
• 2003

This study was to compare the Intake and Committed Effective Dose(CED) due to inhalation of I-131. The Intake and CED Calculations were based on KIDAC, LUDEP, MONDAL and IMBA computer codes.

• 대한방사선방어학회:학술대회논문집
• /
• 2009.04a
• /
• pp.290-291
• /
• 2009

• 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.

• Journal of the Korean Society of Radiology
• /
• v.9 no.2
• /
• pp.109-115
• /
• 2015

In case of a CT examinations, there is a difference in the distribution of radiation dose from that of general X-ray equipments, and it has been known to cause a great radiation exposure during the examinations. However, owing to its high reliability on the accuracy of a examinations result, its use has increased continuously. In consideration of such a circumstance, the CT equipment, radiation dose during CT examinations, diagnostic reference level, and solutions to reduce radiation dose were mentioned on the basis of previously reported data.