• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.235-235
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• 2004

밀봉선원 폐기물은 크기가 작지만 특별한 관리 및 처분을 요하는 방사성폐기물이다. 특히 수거된 폐라듐선원의 경우 장기간의 관리가 필요하며, 음식물 보존이나 살균에 사용된 대형 밀봉선원 폐기물의 경우도 처분보다는 재활용도 고려하여야 한다. 이러한 밀봉선원의 특징은 작은 크기와 고건전성물질로 되어 있고 높은 비방사능을 갖는다는 것이며 따라서 처분시 보통의 방사성폐기물과는 달리 비균질폐기물의 특성을 고려한 안전성 평가가 필요하다.(중략)

• 대한방사선방어학회:학술대회논문집
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• 2009.11a
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• pp.156-157
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• 2009

• Journal of Radiation Protection and Research
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• v.32 no.1
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• pp.35-44
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• 2007

Sealed sources have to conducted the tests be done according to the classification requirements for their typical usages in accordance with the relevant domestic notice standard and ISO 2919. After each test, the source shall be examined visually for loss of integrity and pass an appropriate leakage test. Tests to class a sealed source are temperature, external pressure, impact, vibration and puncture test. The environmental test conditions for tests with class numbers are arranged in increasing order of severity. In this study, the apparatus of tests, except the vibration test, were developed and applied to three kinds of sealed source. The conditions of the tests to class a sealed source were stated and the difference between the domestic notice standard and ISO 2919 were considered. And apparatus of the tests were made. Using developed apparatus we conducted the tests for $^{192}Ir$ brachytherapy sealed source and two kinds of sealed source for industrial radiography. $^{192}Ir$ brachytherapy sealed source is classified by temperature class 5, external pressure class 3, impact class 2 and vibration and puncture class 1. Two kinds of sealed source for industrial radiography are classified by temperature class 4, external pressure class 2, impact and puncture class 5 and vibration class 1. After the tests, Liquid nitrogen bubble test and vacuum bubble test were done to evaluate the safety of the sealed sources.

• The Korean Journal of Nuclear Medicine Technology
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• v.21 no.1
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• pp.50-53
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• 2017

Purpose The change in uniformity due to the decreasement in dose should be known. $^{57}Co$ sealed sources are easy to manage and use as QC sources replacing $^{99m}Tc$. Overlapping sealed sources are expected to show variations in dose due to attenuation between sealed sources. Materials and Methods A total of three experiments were conducted. The first experiment is to observe the change in the degree of senescence of the $^{57}Co$ sealed source. The second experiment is to compare the single source and overlaped source at similar doses. In the third experiment, the sources of different doses were compared on each other to determine the changes due to the attenuation between the overlapping sources. Results The results of the first experiment did not exceed the acceptable range. but each crew showed a difference. There was no statistically significant difference in the measurement of uniformity on second and third experiment Conclusion It is believed that a $^{57}Co$ sealed source can be used as a superimposed source. It is not only economical but also convenient to use. daily uniformity measurements will help reduce scan time and speed up the testing process.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.757-762
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• 1998

“하나로”를 이용하여 강내 조사용으로 사용되는 $^{192}$ Ir 선원의 제조법을 확립하였다. HTS (Hydraulic Transfer System)조사공에서 48시간 조사한 $\psi$2.5 mm x t 0.25 mm의 원판형 Ir 표적 10장을 쌓아서 방사능이 1.012 Ci인 선원을 시험제조하였다. 선원 제작에 관련된 생성방사능, 중성자 자기홉수효과 인자를 이론적으로 계산하여 시험제조에 사용하였고 ${\gamma}$선 자기흡수효과는 실험으로 측정하여 암 치료에 요구되는 10-20 Ci 선원의 상용생산에 필요한 자료를 확보하였다. 치료용 소선원 제작에 관련된 표적제작, 중성자조사, 방사능 측정, 선원조립, 밀봉용접, 품질관리 등의 제작기술을 확립하고 선원의 안전성은 밀봉시험, 표면오염검사 등을 수행하여 확인하였다. 제조된 선원은 실제 사용되는 조사장치에 장착하여 기능시험을 수행할 것이다. 이번 실험을 통하여 강내 조사용으로 사용되는 10-20 Ci 방사능의 $^{192}$ Ir 선원을 안정적으로 공급할 수 있음을 확인하였으며 하나로를 이용하여 캡슐 직경 4 mm의 치료용 소선원 제작기술을 확립하였다. 개발된 /spp 192/Ir 강내 조사용 선원은 국내 5-6개 병원에 공급할 것이며 이 기술을 바탕으로 직경 1.1-1.6 mm의 강내 조사용 선원도 개발할 예정이다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.11 no.4
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• pp.293-301
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• 2013

Borehole Disposal Concept (BDC) was initiated by the South African Nuclear Energy Corporation (NECSA) with the view to improve the radioactive waste management practices in Africa. At a time when geological disposal of radioactive waste is being considered, the need to protect ground water from possible radioactive contamination and the investigation of radionuclides migration through soil and rocks of zone of aeration into ground water has becomes very imperative. This is why the Borehole Disposal Concept (BDC) is being suggested to address the problem. The concept involves the conditioning and emplacement of disused sealed radioactive sources in an engineered facility of a relatively narrow diameter borehole (260 mm). Tanzania is operating a Radioactive Waste Management Facility where a number of spent sealed radioactive sources with long and short half lives are stored. The activity of spent sealed radioactive sources range from (1E-6 to 8.8E+3 Ci). However, the long term disposal solution is still a problem. This study therefore proposing the country to adopt the BDC, since the repository requires limited land area and has a low probability of human intrusion due to the small footprint of the borehole.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.521-522
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• 2005

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.10a
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• pp.281-282
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• 2016

• Proceedings of the Korean Society of Medical Physics Conference
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• 2005.04a
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• pp.42-46
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• 2005

The Dose calculation program for the Buchler remote after-loading system was developed. We use iridium source for the tandem and cessium for the ovoids. We determined the source length and distributions by dividing the program disk to 72 points. The dose rate for the each program disk were calculated and stored to the tables for the xy coordinates. The dose rate for the interesting points for the patients were calculated by using these tables. We also made isodose curve from the calculations. By using the program, we could calculate the dose rate for the various points of the patient quickly and accurately.

• Nuclear industry
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• v.20 no.6 s.208
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• pp.52-54
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• 2000