• Nuclear Engineering and Technology
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• v.2 no.3
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• pp.149-161
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• 1970

This paper describes a detailed investigational performance on the gamma radiation shield effect of heavy concretes that were manufactured by the use of mineral ores produced domestically and which may be possibly applied for the biological shield design. Ten different kinds of mineral ores were collected for use as the aggregates, physical test and chemical analysis for them were carried out to select the aggregate with a better property. Through the experimental investigation on the shielding effect of various concretes with different combination of concrete components such as water-cement and fine-coarse aggregate ratios, it was possible to derive some criteria for the best condition being capable of obtaining the concretes with high density and good uniformity. Data on the shielding-effectiveness of the different concretes were obtained by performing collimated beam experiment using 60Co gamma-ray. Analyzing the shielding-efficiency, shielding-concrete specific gravity and biological shield cost, the optimum condition of yielding the best economic shielding design, with low cost and good spatial distribution to some extent was determined.

• Journal of radiological science and technology
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• v.40 no.2
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• pp.281-287
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• 2017

The purpose of this study is to calculate the thickness of shielding for concrete which is mainly used for radiation shielding and study of the walls constructed to shield medical linear accelerator. The optimal shielding thickness was calculated using MCNPX(Ver.2.5.0) for 10 MV of photon beam energy generated by linear accelerator. As a result, the TVL for photon shielding was formed at 50~100 cm for pure concrete and concrete with Boron+polyethylene at 80~100 cm. The neutron shielding was calculated 100~140 cm for pure concrete and concrete with Boron+polyethylene at 90~100 cm. Based on this study, the concrete is considered to be most efficient method of using steel plates and adding Boron+polyethylene th the concrete.

• Proceedings of the Korea Concrete Institute Conference
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• 2008.11a
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• pp.561-564
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• 2008

Concrete is considered to be one of the excellent and versatile shielding material and is widely used for the radiation shielding material. Specially, heavyweight(or high density) concrete is used in counter weights of bascule and lift bridges, but it is generally used in radiation shielding structures and differ from normal weight concrete by having a higher density and special compositions to improve its attenuation properties. Thorough examination and evaluation of heavyweight aggregate sources are necessary to obtain material suitable for the type of shielding required. Therefore, this paper aims to study mechanical properties of heavyweight concrete by using normal cement, natural and heavyweight aggregate.

• 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.

• Progress in Medical Physics
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• v.15 no.4
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• pp.247-254
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• 2004

According to developing high energy linear accelerators and treatment methods, like (3 dimensional conformal radiotherapy (3D-CRT), intensity modulated radiotherapy (IMRT), many radiotherapy centers are replacing older linear accelerators with new higher technical machines. This often presents a shielding problem as the designed shield for the existing rooms is not adequate for the higher technical machines. Additional shielding in limited existing space becomes necessary. We are replacing older brachytherapy room with new higher technical linear accelerator for IMRT. This room is not adequate for the IMRT machine without additional shielding design. The logical development of optimum structural shielding designs with concrete and high density shielding blocks are presented. We obtained following results by comparison between the pre-calculating values and actual survey of completed LINAC installation. High density shielding blocks have more powerful radiation protection about 2 times.

• Journal of the Korea Institute of Building Construction
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• v.20 no.2
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• pp.129-135
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• 2020

The purpose of this research is to analyze the gamma ray shielding effect of heavy concrete containing magnetic aggregate and to confirm the applicability to the military protective facilities. In general, a military concrete structure protects combatants from bullets, and also it provides some radiation shielding. In this research, experiments were conducted using a Cs-137 source to check the gamma ray shielding effect. In addition, the Monte Carlo N-Particle(MCNP) modeling was applied to evaluate the gamma ray shielding effect of a military structure. As a result, as the concrete thickness increased, the shielding performance improved according th the linear attenuation law. With that, as the ratio of magnetic aggregate was increased, gamma ray shielding performance was also improved. Therefore, this research verified that the application of magnetic aggregate concrete to military facilities for radiation shielding purposes would be useful.

• Progress in Medical Physics
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• v.15 no.4
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• pp.210-214
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• 2004

Since production of radioactive isotope for using PET, a lot of neutrons were produced. The produced neutrons were mainly shielded by concrete facility. Secondary photons are generated and emitted from the concrete shielding wall of the PET cyclotron since the proton-generated neutrons are thermalized and absorbed in the concrete wall and emit secondary radiations, i.e., photons. This study calculated neutron dose and photon dose at outside of the accelerator facility using MCNPX code. As results of the calculation, total dose were calculated less than limited dose by law.

• Magazine of the Korea Concrete Institute
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• v.6 no.6
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• pp.42-50
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• 1994

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05a
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• pp.275-281
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• 1996

ENDF/B-VI 핵단면적자료를 기초로 생성된 BUGLE93$^{[1]}$ 라이브러리를 이용하여 울진 3.4호기 원자로 주변의 콘크리트 일차차폐벽에 대한 방사선차폐해석을 수행하였다. 중성자 및 감마선 수송계산은 일차원 각분할 해석코드인 ANISN-ORNL$^{[2]}$ 을 이용하였다. 또한, 기존의 영광 3.4호기 설계에 이용하였던 CASK$^{[3]}$ 라이브러리를 대체할 경우 예상되는 차폐효과의 변화를 평가하기 위하여 노심으로부터 일차차폐벽 사이의 모든 매질에 대한 중성자 및 감마선속을 계산하고. 계산결과를 비교.분석하여 제시하였다. 중성자선속에 대한 분석결과, BUGLE93을 이용한 계산결과는 원자로용기 내부에서는 CASK를 이용한 결과보다 적은, 보다 현실적인 결과를 제공하지만 일차차폐벽내에서는 CASK를 이용한 결과보다 오히려 큰 선속을 보였다. 그러나 이차감마선에 의한 분석결과는 원자로용기 내부에서의 큰 차이에도 불구하고 일차차폐벽을 통과하면서 두결과가 거의 일치하였다. 이것은 BUGLE93 라이브러리가 노심 및 철성분에 대해서는 증가된 핵단면적을 제공하지만 콘크리트 성분에 대한 핵단면적은 오히려 감소하였기 때문이다. 결론적으로. 최소 7피트 두께의 일차차폐벽 외부에서 중성자선속은 감마선속에 비하여 무시할 수 있을 정도이므로. 원자로 내부영역에서 CASK 라이브러리와는 다른 결과를 보이는 BUGLE93 라이브러리를 원자로 일차차폐벽의 방사선차폐해석에 사용할 경우 기존의 CASK 라이브러리를 이용한 해석결과와 동일한 결과를 보이는 것으로 평가되었다.

• The Journal of Korean Society for Radiation Therapy
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• v.15 no.1
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• pp.11-18
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• 2003

The concrete is usually used to build a radiation therapy facility and the enough concrete thickness for high energy x-ray beam is about 1 meter. But if the space is not enough to build a radiation therapy facility with concrete, the substitute for concrete is needed, and the Ledite can be a good substitute for concrete. In this study, we compared the Ledite with the concrete. The comparing list are the needed shielding thickness, the period of construction and the cost.