• Journal of Astronomy and Space Sciences
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• v.19 no.2
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• pp.151-162
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• 2002

Two approximate calculation models for a cosmic radiation shielding in satellite are compared with detailed 3-dimensional calculation results. One is a sectoring method and the other is a chord-length distribution method. Shielding caltulation is performed for KITSAT-1 under the assumed environment at SAA (South Atlantic Anomaly) location with AP-8 radiation spectrum model. When both approximate models are applied, calculation error is expected compared with 3-D detailed geometry calculation because of straight knock-on assumption neglecting the deflection of incident proton. However, both approximate models showed good agreements with 3-dimensional detailed Monte Carlo calculation in two dose detector locations.

• Journal of radiological science and technology
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• v.33 no.4
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• pp.363-367
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• 2010

In this paper we proposed an easy method to calculate the thickness of primary protective barrier for radiographic equipment. The concrete was selected for the shielding material. The area of protective barrier was divided into a controlled area and a noncontrolled area. For the computation of thickness, the data in NCRP Report 49 and 51 was used. For radiographic equipments whose maximum tubevoltages are 100 and 150 kVp, the thicknesses of concrete were calculated as a function of distance. From the calculated data, four analytical models were acquired by fitting an exponential decay function. From the equations acquired by this study, the thickness of primary protective barrier can be calculated approximately.

• Proceedings of the Korea Water Resources Association Conference
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• 2017.05a
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• pp.131-131
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• 2017

상수관의 노후화로 인해 상수관망의 안정성 확보와 지속적인 용수공급에 대한 신뢰성을 증대시키는 것이 중요해지고 있다. 용수공급시스템을 구성하는 상수관의 파괴가 빈번하게 발생하며, 관 파괴 시에 수리, 교체를 위해서 관망의 일부분은 차폐가 되어 해당 지역의 용수 수요자는 수리, 교체작업이 끝날 때까지 단수가 불가피하다. 이런 불편함과 손실을 최소화하기 위한 방법을 찾는 것은 상수관망의 유지관리에서 중요한 문제이다. 상수관망의 부분적 격리는 오염물에 의한 상수관망의 오염, 테러로 인한 독극물의 유입 시 물질의 확산 방지, 상수관망을 이루는 각종 구조물의 고장수리 및 유지 보수 작업 등의 상황을 위해 필수적이다. 상수관망의 부분적 격리를 분석하기 위해서는 '고립구역'이라는 개념이 필요하다. 관 파괴시 밸브가 닫히면서 해당 관과 연결된 관들 또한 함께 격리되는 부분을 '고립구역'으로 정의한다. 관이 두 개의 밸브를 양 끝에 가지고 있는 경우와 독립적인 절점 또한 하나의 '고립구역'으로 정의할 수 있다. 본 연구에서는 이러한 '고립구역'을 실제 상수관망에서 탐색해서 정의할 수 있는 알고리즘을 제시하였다. 뿐만아니라 상수관 파괴 시 복구를 위해 파괴된 관을 포함한 고립구역이 차폐될 경우, 세그먼트내의 관들은 수원지로부터의 물공급에 차질이 생길 수 있다. 특정 관들의 고립구역이 수원지로부터 유일한 용수공급경로일 경우 고립구역의 차폐로 인해 해당 관들의 용수공급도 끊어지게 되는데 이러한 영역을 '비의도적 고립구간'이라 한다. 본 연구에서는 이러한 '비의도적 고립구간'을 실제 상수관망에서 탐색하여 정의할 수 있는 알고리즘을 제시하였다.

• Applied Chemistry for Engineering
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• v.9 no.6
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• pp.884-888
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• 1998

Effects of heating time under high temperature on the thermal and mechanical properties of neutron shielding materials based on modified (KNS-102), hydrogenated(KNS-106) bisphenol-A type epoxy resin and phenol-novolac(KNS-611) type epoxy resin for radioactive material shipping casks have been investigated. At early stages, the initial decomposition temperatures of the shielding materials of KNS-102, KNS-106 and KNS-611 increased with the heating time under high temperature, but it was rarely affected by the heating time in the later stages. In addition, the thermal conductivities of KNS-102 and KNS-106 decreased with heating time, but that of KNS-611 increased with the heating time. On the contrary, the thermal expansion coefficients of neutron shielding materials decreased with increase of heating time. At the high temperature, the tensile strength and flexural strength of the shielding materials of KNS-102 and KNS-611 increased with heating time, but those of KNS-106 decreased with increase of heating time. And the heating time under high temperature on the neutron shielding materials did not show measurable loss of weight and hydrogen content.

• Journal of Radiation Protection and Research
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• v.4 no.1
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• pp.14-20
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• 1979

For accurate and easily shielding irregular shaped organ, its minimized penumbra region and a low melting point alloy 'Lead Y' and synchronizing instrument have been developed. The 'Lead Y' is the quaternary eutectic alloy and it is composed of Lead 30.0% Tin 11.5% Bismuth 48 5% Cadmium 10.0% The density of its at $22^{\circ}C$ is $9.8g/cm^3$ and the melting temperature has $40^{\circ}C\;to\;68^{\circ}C$. The thickness of 'Lead Y' for perfect shielding of Co-60 gamma ray and LINAC 10MeV x-ray is 6cm and 7cm respectively. The 'Lead Y' shielding block is casted directly on the styrofoam from which is cut with hot wire of synchronizer device. The special features and advantages of the Lead Y shielding block could be summarized as follows; 1. The shielding block for radiotherapy is rapidly processed only with boiling water and styrofoam. 2. It is not injure one's health and not danger of a fire, because of not generating of any metals vapor and evil smelling. 3. It is very effective to minimize secondary penumbra for the protection of healthy tissue from unnecessary ionizing radiation regardless of the magnification source to skin distance. 4. The HVL of the Lead Y is 1.2cm for Co-60 gamma ray and it's shielding effect is almost same as the pure lead block. 5. The hardness of Lead Y is 1.5 times higher than lead block. 6. It's reavailability is higher than lead block and then one block of Lead Y is reavailable about 30 to 40 times. 7. It is usefull for shielding of x-ray, gamma ray, beta-ray, electron and neutron radiation. 8. The materials for Lead Y are easy to acquire with reasonable price and tractable.

• Applied Chemistry for Engineering
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• v.8 no.3
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• pp.524-532
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• 1997

ffects of radiation on the thermal and mechanical properties of modified epoxy resin and hydrogenated bisphenol-A type epoxy resin based neutron shielding materials to be used for radioactive material shipping and storage casks have been investigated. The onset temperatures of the shielding materials of KNS(Kaeri Neutron Shield)-201 and KNS-302 increased with the radiation dose, but those of KNS-202 and KNS-301 decreased at radiation dose above 0.5 MGy. In addition, the radiation dose rarely affected the change of weight of shielding materials with the variation in temperature. At radiation dose up to 0.1 MGy, thermal conductivities of shielding materials were not affected. The thermal expansion coefficients of the shielding materials of KNS-301 and 302 were affected to a less extent than those of KNS-201 and 202 by radiation. At radiation dose up to 0.1 MGy, the tensile strength, compressive strength and flexural strength of the shielding materials of KNS-202 and KNS-301 and 302 increased with the radiation dose. In contrast, those of KNS-201 decreased with an increase in the radiation dose. In addition, the amount of radiation dose on the shielding materials did not result in a measurable loss of specific gravity, weight and hydrogen content.

• Journal of radiological science and technology
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• v.4 no.1
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• pp.15-22
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• 1981

Half value layer(radiation energy) of $90^{\circ}$ scattered radiation from various radiation shielding materials was measured at 1 m distance from the central ray of the primary beam. Scattered radiation was measured from 100 to 200 kVp for 0-2.0mm Cu+1.0mm Al added filter in the primary beam for a deep therapeutic unit, the obtained results were as follows: 1. The ratio of scattered radiation to primary radiation was increased by using lighter filter. 2. The ratio of scattered radiation to primary radiation was decreased by using heavier filter. 3. The ratio of scattered radiation to primary radiation was independent of tube voltage. 4. The scattered radiation of high energy was produced, when the effective atomic number and density of shielding material were high.

• Journal of radiological science and technology
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• v.26 no.1
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• pp.45-50
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• 2003

In this work, we characterized the shieldability and lightweight of radiation protective aprons which were consisted of various metal(Pb, Sn, Ni, Ti and Cu) by measuring the x-ray dose transmitted through the filters. The transmitted ratio and lead equivalent of various metal were obtained by linear interpolation and the lead equivalent of double layered filters contained Pb layer was determined. The transmitted ratio of the apron(0.25 mmPb) specified in KS B 0845 was 5.2%. The transmitted ratio of the filters at the thickness of 0.6 mm was decreased in the other of Ni(32.60%), Ti(17.75%), Cu(13.25%) and Sn(3.84%). From the results of experimental evaluation for combined filter of Pb and Sn, it was founded that in the case of the first Sn layer, the lead equivalent was higher than that of the first Pb layer. The lead equivalent corresponding to apron of 0.25 mmPb was obtained in the double layered filters of Sn(0.19 mm) - Pb(0.1 mm) and Pb(0.1 mm) - Sn(0.37 mm). Thus, the Sn-Pb filter had the lower weight about 13% than apron of 0.25 mmPb.

• Journal of the Korean GEO-environmental Society
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• v.5 no.4
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• pp.57-63
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• 2004

In general steel sheet piles are used in the containment system, which are vertical barrier systems for waste disposal and landfill purposes, and roads in excavation for temporary structure. This paper presents case study of the use of an interlocking sheet pile for water and containment. Cut-off Z-type sheet pile joints are investigated to determine their permeability from the field test. Four different joint sealing materials are used in field test. The results showed joint permeability is significant time-dependent and joint-dependent. These are explored and conclusions on permeability characteristics of different sealants are noted. A case study gives a design example as well as suggestion on permeability and water tightness can be implemented in using the sheet pile barrier in civil and environment works. From the test results, the effective sealing programs of sheet pile interlocks are suggested.

• The Journal of Korea Institute of Information, Electronics, and Communication Technology
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• v.13 no.1
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• pp.27-34
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• 2020

Human access is restricted to environment where radiation sources are used, however observation equipment should be radiation-resistant as it is exposed. Therefore, if tungsten with the highest specific gravity and melting point and the lowest lead were selected to reduce the dose to the Cobalt 60 radiation source to 1/8, Tu had a volume of 432.6cm3, a thickness of 2.4cm, and Pb had a volume of 961cm3,, a thickness of 3.6cm. By applying this method, produced a radiation resistant CMOS camera with a camera module using a CMOS Image sensor and a radiation shielding structured housing. As a result of applying the head detachable 2M AHD camera (No. ①) that survived the experiment to select the optimal shielding thickness, when shielding the associated equipment such as cameras, adapters, etc. is achieved, it was confirmed that the design of the structure is appropriate by operating well at doses higher than 1.88×106rad. Therefore, it is expected to secure the camera technology and business feasibility that can be applied to high radiation environments.