• Proceedings of the Korea Air Pollution Research Association Conference
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• 2003.11a
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• pp.229-230
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• 2003

중성자 방사화분석법은 핵반응을 통해 생성시킨 방사성 동위원소로부터 방출되는 방사선을 검색하여 절대적으로 성분원소를 정량하는 핵분석기술(Nuclear Analytical Techniques)이다. 현재 한국원자력연구소의 중성자 방사화분석실에서는 대기환경분야 응용연구로서 수년 동안 대기분진을 채집하여 미량 성분원소를 정량하고 있으며, 방법의 유효화와 측정결과의 신뢰성을 확보하기 위하여 시료의 채집 및 준비, 원소분석, 측정결과의 검증 등 분석과정에 대한 품질관리를 수행하고 있다. (중략)

• Analytical Science and Technology
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• v.15 no.6
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• pp.521-528
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• 2002

Neutron Activation Analysis (NAA) and Inductively Coupled Plasma Atomic Emission Spectrometry (ICP-AES) have been applied for the determination of inorganic elements in mud flat of south seaside in Korea. The analytical results of Al, Ca, Fe, Mg, K and Na by NAA were compared with those by ICP-AES. The results show that NAA is superior to ICP-AES for the determination of minor elements in sediment. Accordingly, NAA will play an important role in the analysis of environment samples such as mud flat and sediment having complex matrix.

• Proceedings of the Korea Information Processing Society Conference
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• 2018.10a
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• pp.795-796
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• 2018

방사광은 기존 기계학적인 방법으로 분석했던 연구보다 더 정확한 관찰이 가능해 신뢰도가 높은 결과를 얻을 수 있다. 본 연구의 목적은 흰쥐 정강뼈의 미세구조를 3차원적으로 분석 가능한 방사광기반 경X선을 이용해 골다공증의 진단 및 평가에 필요한 정량화된 분석을 구축하고자 하였다. 흰 쥐의 정강뼈를 방사광을 통해 해부학 구조 및 미세내부구조를 얻은 뒤 3차원적 구조분석을 하였다. 그 후, 방사광으로 얻은 영상 데이터를 통해 뼈 내부 구조를 높은 해상도 이미지로 시각화하여 분석을 할 수 있었다. 따라서, 골다공증과 관련된 퇴행성 골격질환의 정량화된 분석방법을 제시하여 근거중심의 평가와 예방의 기초자료가 될 것으로 기대한다.

• 대한방사선방어학회:학술대회논문집
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• 2009.04a
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• pp.138-139
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• 2009

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• Journal of the Korean Society of Radiology
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• v.13 no.1
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• pp.45-53
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• 2019

This study is a neutron activation for concrete that shields medical linear accelerator facilities. Comparison of general concrete and low activation concrete. The simulation method was simulated using MCNPX (Ver. 2.5.0) and FISPACT-2010, and the shielding ability for photon and neutron beams was calculated and neutron activation evaluation was carried out. As a result, the shielding capacity was 20 ~ 50 cm efficient in general concrete, and activate evaluation in low activation concrete was calculated to be low in radioactivity concrete, but all were estimated to not exceed their own allowable concentration in self - disposal. As a result of the comprehensive analysis, it is considered effective to use ordinary concrete.

• Journal of the Korean Society of Radiology
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• v.10 no.7
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• pp.489-494
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• 2016

Nuclear reaction which occurs in the cyclotron generate unnecessary neutrons. The results of this happening can radioactivate surrounding materials and radioactive materials cause radiation exposure. When people take radioactive air, it makes internal exposure. The purpose of this study was to analyze the radioactive air inside of the ultra-compact 16.5 MeV cyclotron in operation. As a result of study, the radio activation occurred by compact cyclotron generates a very low internal exposure to workers. Comparing the radioactivity from radioactive nuclide with legal standard, that was under reference value. However, it could be at risk for internal exposure in case of higher energy cyclotron. Therefore, legal standard is needed for ventilation equipment of radiation facilities.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.14 no.2
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• pp.91-100
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• 2016

The neutron activation inventories in reactor vessel and its internals, and bio-shield of a PWR nuclear power plant were calculated to evaluate the effect of impurity elements contained in the structural materials on the activation inventory. Carbon steel is, in this work, used as the reactor vessel material, stainless steel as the reactor vessel internals, and ordinary concrete as the bio-shield. For stainless steel and carbon steel, one kind of impurity concentration was employed, and for ordinary concrete five kinds were employed in this study using MCNP5 and FISPACT for the calculation of neutron flux and activation inventory, respectively. As the results, specific activities for the cases with impurity elements were calculated to be more than twice than those for the cases without impurity elements in stainless and carbon steel. Especially, the specific activity for the concrete material with impurity elements was calculated to be 30 times higher than that without impurity. Neutron induced reactions and activation inventories in each material were also investigated, and it is noted that major radioactive nuclide in steel material is Co-60 from cobalt impurity element, and, in concrete material, Co-60 and Eu-152 from cobalt and europium impurity elements, respectively. The results of this study can be used for nuclear decommissioning plan during activation inventory assessment and regulation, and it is expected to be used as a reference in the design phase of nuclear power plant, considering the decommissioning of nuclear power plants or nuclear facilities.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.11a
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• pp.96-97
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• 2005

• The Journal of the Korea Contents Association
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• v.17 no.9
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• pp.69-76
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• 2017

This study evaluated the activation of the shielding wall and the components around the accelerator by using the medical linear accelerator. We performed simulations for energy values of 20 MV with the operating time ranging from day 1 to 30 years, and linear accelerator head and shielding wall concrete were also evaluated. The results showed that neutrons in large quantities were analyzed using high energy around thetarget point where photons were formed. Based on the activation analysis with these results, radioactivity increased with an increase in operation time and activated nuclides usually start saturating in10 years. Furthermore, the general types of nuclides formed owingto the activation were Co-60, W-181, 185, 187, Na-24, Ca-45, Mn-54, 56, and Fe-55, 59.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.05a
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• pp.187-188
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• 2012