• Nuclear Engineering and Technology
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• 제40권4호
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• pp.319-326
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• 2008

To transport process wastes efficiently from the Advanced Spent Fuel Conditioning Pyro-process Facility (ACPF) at the Korea Atomic Energy Research Institute (KAERI), a new hot cell cask has been designed based on an existing hot cell padirac transport cask, with not only a neutron absorber for improved shielding capability, but also a docking facility for an easy docking system. In the new hot cell cask, two kinds of materials have been considered as shielding materials, polyethylene and resin. To verify the transport compatibility of the waste and spent fuel for the ACPF, neutron and photon shielding calculations were performed using the MCNPX code. The source term was evaluated by the ORIGEN-ARP code system based on spent PWR fuel. From the calculation, it was found that the maximum surface dose rates of the hot cell cask with the two candidates were estimated within the limit (2 mSv/hr).

• Journal of Radiation Protection and Research
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• 제21권1호
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• pp.17-25
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• 1996

본 연구에서는 사용 후 핵연료의 안전수송을 위한 수송용기의 설계/해석 항목 중 용기 내부에 장전한 핵연료에서 방출되는 중성자의 방사선량률을 효과적으로 평가하는 방법을 구축하기 위하여 수송용기의 방사선차폐해석을 기존의 해석 수행방법인 결정론적인 방법으로 수행하고 확률론적인 방법으로 그 결과를 검증하였다. 결정론적 방법을 이용한 해석코드로 Discrete Ordinate 방법의 DOT4.2 코드를 사용하였으며, 이에 대한 비교와 검증을 위한 확률론적 방법의 차폐해석 코드로는 Monte Carlo 해법의 해석코드인 MCNP4A을 이용하였다. 동일한 대상물에 대한 방사선량율에 대한 평가를 두 방법으로 수행한 결과 두 방법으로부터의 해석결과는 큰 차이를 보이지 않았다. 이 결과비교를 통하여 사용후 핵연료 수송용기에 대한 방사선량율 평가가 올바르게 수행된 것을 확인할 수 있었고 또한 설계 및 해석에 관한 품질보중사항이 규정된 10CFR71 appendixH의 설계해석 및 전산코드 검증에 따한 요구조건을 만족시킬 수 있었다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(2)
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• pp.618-623
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• 1998

A shielding analysis was performed for the end shield of CANDU 6 reactor. The one-dimensional discrete ordinate code ANISN with a 38-group neutron-gamma library, extracted from DLC-37D library, was used to estimate the dose rate for the natural uranium CANDU reactor. For comparison MCNP-4B calculation was performed for the same system using continuous, discrete and multi-group libraries. The comparison has shown that the total dose rate of the ANISN calculation agrees well with that of the MCNP calculation. However, the individual dose rate (neutron and gamma) has shown opposite trends between AMISN and MCNP estimates, which may require a consistent library generation for both codes.

• 한국의학물리학회지:의학물리
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• 제1권1호
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• pp.61-68
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• 1990

We have designed the calculation model(AMC method) of electron output for the cut-out fieldsand studied the influence of shielding block size. The output of electron was measured in the water phantom at dmax, for 20 $\times$ 20cm$^2$ cone size electron beams from CL/1800 linear accelerator(Varian, USA), Which generates the energy of 6, 9, 12, 15 and 18MeV electron beams. The shielding blocks were rectangular or squre shaped, low melting point alloy. We can predict the output from the arbitrarily rectangular shaped block within 1% error. by using the AMC method, which considers the contribution of the collimator(block) scatter and the phantom scatter.

• 대한전기학회논문지
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• 제31권12호
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• pp.173-179
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• 1982

This paper presents a modified quasi-static approximate solution derived from the Maxwell's equations of integral form for the calculation of magnetic shielding effectiveness in a non-uniform enclosure such as metal-clad high-voltage test laboratory. It also describes the simplified relationship between the electrical parameters applicable to the engineering calculations of electromagnetic absorption loss which comprise the resultant effects due to the welding seams and short-circuited slots as well as the shielding material properties. A numerical example shows the fairly good agreements with experimental results measured on the absorption loss vs. incident wave frequency without any unreasonable rapid increase.

• International Journal of Contents
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• 제14권4호
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• pp.65-69
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• 2018

The objective of this study was to conduct a radiation shielding analysis for the facility equipped with radiation generator. The analysis was carried out in two aspects. First, from the aspect of the effect caused by primary and leakage radiation. Second, effect of scattered radiation was evaluated by applying a simple calculation method based on a scattering rate concept since effect of scattered radiation is significantly important at maze entrance of the radiation facility. The calculated results obtained using the simple method were compared to the results calculated using Geant4 code and the measured values. The results calculated by the suggested method indicate that slight error exists in a radiation shielding analysis done at the maze entrance comparing to other two results, while the results evaluated at the outside of the maze entrance door are relatively consistent with other values.

• 전기의세계
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• 제29권1호
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• pp.65-72
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• 1980

Arstrong-Whitehead theory on effective shielding and shielding failure is extended so that it is applicable to vertical line configuration the existing approaches on back-flash rate calculation are summerized and compared in particular on Model Line, and the usefulness of the whitehead approach is suggested.

• Nuclear Engineering and Technology
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• 제52권6호
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• pp.1137-1147
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• 2020

The discrete ordinates method (S_N) is one of the major shielding calculation method, which is suitable for solving deep-penetration transport problems. Our objective is to explore the available quadrature sets and to improve the accuracy in shielding problems involving strong anisotropy. The linear discontinuous finite-element (LDFE) quadrature sets based on the icosahedron (in short, ICLDFE quadrature sets) are developed by defining projected points on the surfaces of the icosahedron. Weights are then introduced in the integration of the discontinuous finite-element basis functions in the relevant angular regions. The multivariate secant method is used to optimize the discrete directions and their corresponding weights. The numerical integration of polynomials in the direction cosines and the Kobayashi benchmark are used to analyze and verify the properties of these new quadrature sets. Results show that the ICLDFE quadrature sets can exactly integrate the zero-order and first-order of the spherical harmonic functions over one-twentieth of the spherical surface. As for the Kobayashi benchmark problem, the maximum relative error between the fifth-order ICLDFE quadrature sets and references is only -0.55%. The ICLDFE quadrature sets provide better integration precision of the spherical harmonic functions in local discrete angle domains and higher accuracy for simple shielding problems.

• Journal of Electrical Engineering and Technology
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• 제6권6호
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• pp.760-768
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• 2011

The performance of transmission lines and its shielding design during a lightning phenomenon are quite essential in the maintenance of a reliable power supply to consumers. The leader progression model, as an advanced approach, has been recently developed to calculate the shielding failure rate (SFR) of transmission lines using geometrical data and physical behavior of upward and downward lightning leaders. However, such method is quite time consuming. In the present paper, an effective method that utilizes artificial neural networks (ANNs) to create a metamodel for calculating the SFR of a transmission line based on shielding angle and height is introduced. The results of investigations on a real case study reveal that, through proper selection of an ANN structure and good training, the ANN prediction is very close to the result of the detailed simulation, whereas the Processing time is by far lower than that of the detailed model.

• 한국위성정보통신학회논문지
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• 제3권1호
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• pp.35-40
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• 2008

본 논문에서는 위성용 전자 부품 또는 장비를 내장한 함체의 개구가 유전체로 막힌 경우 차폐효과를 계산하는 해석적 방법을 제안한다. 차폐효과는 주파수, 유전체의 유전율, 함체 내에서 차폐효과를 정의하는 위치에 영향을 받는다. 또한, 유전체 판의 일부가 도체로 막혀 있는 경우도 해석하였다. 계산 결과를 보면, 유전체에 의하여 함체 공진의 Q 값이 감소되었으며, 개구에서 멀어질수록 차폐효과 개선되는 것을 확인 할 수 있었다.