• The Proceedings of the Korean Institute of Illuminating and Electrical Installation Engineers
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• v.5 no.1
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• pp.40-45
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• 1991

This paper proposes a simplifying model for the calculation of the radiant flux and radiation energy in an RD (Radiation Dominated) arcplasma. Defects of the previous models are that the radiant flux and radition energy must be numerically solved by the three dimensional integration, and these calculations demand enormous computing time. Thses attribute to the global properties of radiation transfer. This paper suggests a simple calculation technique of radiation characteristics by considerig the relation between the plasma states and the radiation transfer process and by the systematic tabulation of the relation.

• Journal of Radiation Protection and Research
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• v.36 no.1
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• pp.44-51
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• 2011

Activation foil-based Bonner sphere spheres are used to obtain neutron energy spectra of nuclear power plants or accelerator-produced neutrons. The position and the foil mass dependence of response functions should be studied carefully before measurement of Bonner spheres. This study showed that the normal incidence to the foil surface made a large shift of responses while parallel and isotropic incidence made no position dependence. The correlation between foil mass and response was not linear. Therefore, the response functions of activation-foil based Bonner spheres should be calculated for every different foil mass and the direction of Bonner spheres for parallel incidence will be preferred for radioactive neutron source or accelerator target produced neutrons.

• The Proceedings of the Korean Institute of Illuminating and Electrical Installation Engineers
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• v.5 no.4
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• pp.3-7
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• 1991

This paper proposes a simplifying model for the calculation of the radiant flux and radiation energy in an RD(Radiation Dominated) arcplasma. Defects of the previous models are that the radiant flux and radition energy must be numerically solved by the three dimensional integration, and these calculations demand enormous computing time. These attribute to the global properties of radiation transfer. This paper suggests a simple calculation technique of radiation characteristics by considering the relation between the plasma states and the radiation transfer process and by the systematic tabulation of the relation.

• 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.

• Journal of Radiation Protection and Research
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• v.15 no.2
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• pp.51-56
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• 1990

The dispersing model of radioactive plume in the atmosphere was assumed to form finite ellipseshaped volumes rather than a single plume and gamma absorbed doses from the plume were computed using the proposed model. The results obtained were compared with those computed by the Gaussian plume and the circular approximation models. The results computed by the proposed ellipse-shaped approximation model were close to those by the Gaussian plume model. and more accurate than those by the circular approximation model. The computing time for the proposed approximation model was one fortieth of that for the Gaussian plume model.

• 대한방사선방어학회:학술대회논문집
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• 2010.04a
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• pp.162-163
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• 2010

• Proceedings of the Acoustical Society of Korea Conference
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• autumn
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• pp.227-230
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• 2000

본 논문에서는 외부방사 문제에 널리 사용되는 음향경계 요소 법(Acoustic Boundary Element Method)을 확장하여 저주파수 대역은 기존의 방법을 이용하고 고주파수 대역에서는 경계요소의 특성길이에 의한 고주파수 상한을 극복할 수 있는 방법을 제시한다. 밴드를 대표하는 음압 레벨을 직접 계산하도록 상호상관도 가정을 통하여 간략화 하였다. 간단한 음향방사 모델인 배플이 있는 빔과 평판에 대하여 Rayleigh 적분식의 계산결과와 제안된 방법을 비교하여 적용효능성을 검토하였다. 적용을 위한 조건으로는 방사면 진동의 상호상관도가 작아야 하므로, 이를 만족시키기 위한 일반적인 조건식을 제시하여 이로부터 경계요소의 특성길이를 정하는 기준을 제시하였다.

• 대한방사선방어학회:학술대회논문집
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• 2011.11a
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• pp.378-379
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• 2011

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.10a
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• pp.181-182
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• 2016

• 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.