• Proceedings of the Materials Research Society of Korea Conference
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• 2003.03a
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• pp.236-236
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• 2003

• 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.

• Journal of Radiation Protection and Research
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• v.6 no.1
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• pp.34-40
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• 1981

The logical development of an optimum structural shielding design and the computation of protective barriers for high energy radiation therapy room, Toshiba 13 MeV. are presented. We obtained following results by comparison in between the precalculating values and actual survey after complete installation of radiogenerating units. 1. The calculating formula for the protective barrier written in NCRP report #34(1970) was the most ideal and economic calculating methods for the construction of barrier and to determine thickness for the meeting requirements of the number of patients of 80-100 in daily treatment. 2. The precalculating values of protective barrier are 5 times more protective than that of actual measurement. It is depending on radiation workload and utilization the datas most sequrely. 3. The dose rate during exposure are 2-10 mR/hr at out of the door and the controll room. 4. The foul smelling and ozone gas production from long exposure of cancer patients cannot be eliminated when the room is ill ventilated.

• Journal of the Korean Recycled Construction Resources Institute
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• v.7 no.4
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• pp.316-322
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• 2019

A probabilistic approach considering uncertainties was employed to investigate the effects on the material characteristics and strength of nuclear bio-logical shield concrete walls, when exposed to long-term radiation during the entire service life. Time-dependent compressive and tensile strengths were estimated by conducting the neutron fluence analysis. For the contaminated concrete, individual compressive and tensile failure probabilities can be possibly evaluated by not only establishing limit-state function withthe predefined critical values but also performing Monte Carlo Simulation. Nuclear power plant types similar to the Kori Unit 1, which was shut off permanently in 2017 after the 40-year operation, were herein selected for an illustrative purpose. Consequently, the probability-based performance assessment and prediction of contaminated concrete walls were well demonstrated.

• Composites Research
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• v.19 no.3
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• pp.1-6
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• 2006

As the structures of the high performance electronic equipments and devices recently become more complex, the electromagnetic interference (EMI) and compatibility (EMC) have been very essential for commercial and military purposes. Thus, sensitive electrical devices and densely packed systems need to be protected from electromagnetic wave. In this research, glass fabric/epoxy composites containing conductive multi-walled carbon nanotube (MWNT) and carbon fiber/epoxy composites as electrical shielding materials were fabricated and electrical properties of the composites were measured. The concerning frequency band is from 300 MHz to 1 GHz. The performances of composite shielding enclosures were predicted using electromagnetic wave 3-D simulation tool, CST Microwave Studio. The shielding enclosure made of carbon fiber/epoxy composites were fabricated and the shielding effectiveness (SE) was measured in the anechoic chamber.

• Magazine of RCR
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• v.16 no.3
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• pp.21-27
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• 2021

• Journal of the Korea Academia-Industrial cooperation Society
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• v.11 no.3
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• pp.1035-1039
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• 2010

Activation products generated by photoneutrons in concrete shielding wall around electron linac were estimated for a high energy X-ray container cargo inspection system. Monte carlo code, MCNPX2.5.0 was used for reference system of 9MeV fixed type dual-direction container cargo inspection system installed at major harbors in Korea. Activation products inventory generated by photoneutron (n,$\gamma$) reaction are estimated, and then radiation dose rate is calculated from the results.

• Polymer(Korea)
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• v.36 no.4
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• pp.494-499
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• 2012

In this work, the effect of multi-walled carbon nanotube (MWCNT) on electromagnetic interference shielding effectiveness (EMI SE) and mechanical properties of MWCNT-reinforced polypropylene (PP) nanocomposites were investigated with varying MWCNT content from 1 to 10 wt%. Electric resistance was tested using a 4-point-probe electric resistivity tester. The EMI SE of the nanocomposites was evaluated by means of the reflection and adsorption methods. The mechanical properties of the nanocomposites were studied through the critical stress intensity factor ($K_{IC}$) measurement. The morphologies were observed by scanning electron microscopy (SEM). From the results, it was found that the EMI SE was enhanced with increasing MWCNT content, which played a key factor to determine the EMI SE. The $K_{IC}$ value was increased with increasing MWCNT content, whereas the value decreased above 5 wt% MWCNT content. This was probably considered that the MWCNT entangled with each other in PP due to an excess of MWCNT.

• Journal of the Korea Convergence Society
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• v.12 no.10
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• pp.129-136
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• 2021

Radiation shields used in medical institutions mainly use lead to manufacture products and fitments. Although lead has excellent processability and economic efficiency, its use is being reduced due to environmental issues when it is disposed of. In addition, when used for a long time, there is a limit to using it as a shielding film, shielding wall, medical device parts, etc. due to cracking and sagging due to gravity. To solve this problem, copper, tin, etc. are used, but tungsten is mostly used because there is a difficulty in the manufacturing process to control the shielding performance. However, it is difficult to compare with other shielding materials because the characteristics according to the type of tungsten are not well presented. Therefore, in this study, a medical radiation shielding sheet was manufactured in the same process using pure tungsten, tungsten carbide, and tungsten oxide, and the particle composition and shielding performance of the sheet cross-section were compared.As a result of comparison, it was found that the shielding performance was excellent in the order of pure tungsten, tungsten carbide, and tungsten oxide.

• Proceedings of the Korean Vacuum Society Conference
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• 2010.02a
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• pp.274-274
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• 2010

한국은 국제핵융합실험로 (ITER) 사업에 참여하고 있으며, 삼중수소 증식을 시험하기 위한 시험 모듈(TBM, Test Blanket Module)로서 HCML (Helium Cooled Molten Lithium) TBM을 설계, 개발하고 있다. 헬륨 및 액체 리튬을 냉각재와 증식재로 사용하는 개념으로, 구조재로서 Ferritic Martensitic (FM) 강이 사용될 예정이다. 특히, HCML TBM의 일차벽은 중성자 및 플라즈마로부터 입사되는 입자들을 차폐하기 위한 Be 차폐체와 FM강으로 구성되어 있으며, 일차벽 제작법 개발을 위해서는 Be과 FM강 간의 접합과 FM강 간의 접합 방법이 개발되어야 한다. FM강 간의 접합은 기존의 연구를 통해 접합 조건이 이미 도출되었고, 고열부하 시험을 통해 검증 완료한 상태이다. 그러나, Be과 FM강 간의 접합은 현재 개발단계에 있다. 본 논문에서는 고려 중인 구조재와 Be 차폐체 사이의 접합법 개발을 위해, 고온등방가압(HIP, Hot Isostatic Pressing) 조건을 도출하고, 운전조건과 유사 혹은 가혹한 조건에서 고열부하를 인가하여, 그 건전성을 평가하는 일련의 과정을 기술하였다. 본 연구에서는 Be과 FM강 간의 접합법 개발 및 검증을 위해 제작된 $80{\times}80{\times}1$ Be/FM강 mock-up을 국내에서 구축된 고열부하 시험 장비인 KoHLT를 활용하여 수행한 고열부하 시험에 대한 것이다. 본 mock-up은 $80{\times}80{\times}10mm(t)$의 Be tile 3개를 동일 크기에 두께가 각각 25mm와 50 mm인 FM강과 스테인레스강에 접합된 것으로, 고열부하 장비에 설치하여 고열부하 시험을 수행하였다. 냉각수의 온도 및 속도는 25 C, 0.15 kg/sec로 유지되었고, 열부하는 $0.5\;MW/m^2$로 유지하였다. 시험 조건에 대한 예비해석을 통해, 가열시의 온도 및 stress, strain 분포를 얻었고, 이를 통해, cycle to failure 값을 도출하였다. 1000 사이클의 가열 실험을 마친후 초음파를 활용한 접합 계면의 결함확인 및 파괴검사를 통한 접합 건전성을 확인하였다. 3가지 접합법 모두 일부 접합면이 이탈되었으며, 향후 보다 건전한 접합방법 개발이 진행되어야 할 것으로 보인다.