• 대한방사선치료학회지
• /
• 제7권1호
• /
• pp.92-96
• /
• 1995

All patients who will Undergo irraidiation of the oral cavity cancer will need dental before and during Radiotherapy. The extent of the region and the presence of numerous critical normal tissues(mucosa, gingiva, teeth and the alveolar ridge, alveolar bony structure, etc) in the oral cavity area, injury to which could result in serious functional impairment. Therefore I evaluate the Usefulness of custom-made intraoral shielding device before and during Radiotherapy in oral cavity cancer. Materials and Methods(1) : Manufacture process of Custom-made intraoral shielding device Containing Cerroband. A. Acquisition of impression B. Matrix Constitution C. Separation by Separator D. Sprincle on method E. Trimming F. Spacing G. Fill with Cerroband Materials and Methods (2) A. Preannealing B. TLD Set up C. Annealing D. TLD Reading = Results = Therefore dosimetric characteristics in oral cavity by TLD Compared to isodose curve dose distribution Ipsilateral oral mucosa, Contralateral oral mucosa, alveolar ridge, tongue, dose was reduced by intraoral shielding device containning Cerroband technique Compard to isodose plan = Conclusions = The custom-made intra-oral shielding device containing Cerroband was useful in reducing the Contralateral oral mucosa dose and Volume irradiated.

• Nuclear Engineering and Technology
• /
• 제52권1호
• /
• pp.178-184
• /
• 2020

The traditional methods for radiation shield design always only focus on either the structure or the components of the shields rather than both of them at the same time, which largely affects the shielding performance of the facilities, so in this paper, a novel method for designing the structure and components of shields simultaneously is put forward to enhance the shielding ability. The method is developed by using the genetic algorithm (GA) and the MCNP software. In the research, six types of shielding materials with different combinations of elements such as polyethylene (PE), lead (Pb) and Boron compounds are applied to the radiation shield design, and the performance of each material is analyzed and compared. Then two typical materials are selected based on the experiment result of the six samples, which are later verified by the Compact Accelerator Neutron Source (CANS) facility. By using this method, the optimal result can be reached rapidly, and since the design progress is semi-automatic for most procedures are completed by computer, the method saves time and improves accuracy.

• 한국해양공학회지
• /
• 제23권3호
• /
• pp.35-39
• /
• 2009

The main objective of this study was to investigate fiber reinforced composite materials (FRCM) with electromagnetic shielding characteristics using aluminum (Al) film and copper (Cu) meshes. This study investigated the electromagnetic interference (EMI) shielding effectiveness (SE) of fiber reinforced composites filled with Al film, Cu meshes, and nano carbon black as hybrid conductive fillers to provide the electromagnetic shielding property of the fiber reinforced composites. The coaxial transmission line method of ASTM D 4935-89 was used to measure the EMI shielding effectiveness of composites in the frequency range of 300 MHz to 1.5 GHz. The variations of SE of FRCM with Al film, fine Cu, and general Cu meshes are described. The results indicate that the FRCM having Al film exhibited up to 75 dB of SE at 1.5 GHz.

• Nuclear Engineering and Technology
• /
• 제52권3호
• /
• pp.647-653
• /
• 2020

Stainless steel is used commonly in nuclear applications for shielding radiation, so in this study, three different types of new stainless steel samples were designed and developed. New stainless steel compound ratios were determined by using Monte Carlo Simulation program Geant 4 code. In the sample production, iron (Fe), nickel (Ni), chromium (Cr), silicium (Si), sulphur (S), carbon (C), molybdenum (Mo), manganese (Mn), wolfram (W), rhenium (Re), titanium (Ti) and vanadium (V), powder materials were used with powder metallurgy method. Total macroscopic cross sections, mean free path and transmission number were calculated for the fast neutron radiation shielding by using (Geant 4) code. In addition to neutron shielding, the gamma absorption parameters such as mass attenuation coefficients (MACs) and half value layer (HVL) were calculated using Win-XCOM software. Sulfuric acid abrasion and compressive strength tests were carried out and all samples showed good resistance to acid wear and pressure force. The neutron equivalent dose was measured using an average 4.5 MeV energy fast neutron source. Results were compared to 316LN type stainless steel, which commonly used in shielding radiation. New stainless steel samples were found to absorb neutron better than 316LN stainless steel at both low and high temperatures.

• Nuclear Engineering and Technology
• /
• 제52권11호
• /
• pp.2613-2619
• /
• 2020

This work investigated the gamma-ray shielding performance, and the physical and mechanical properties of poly (methyl methacrylate) (PMMA) composites embedded with 0-44.0 wt% bismuth trioxide (Bi₂O₃) fabricated by the fast ultraviolet (UV) curing method. The results showed that the addition of Bi₂O₃ had significantly improved the gamma shielding ability of PMMA composites. Mass attenuation coefficient and half-value layer were examined using five gamma sources (Cs-137, Ba-133, Cd-109, Co-57, and Co-60). The high loading of Bi₂O₃ in the PMMA samples improved the micro-hardness to nearly seven times that of the pure PMMA. With these enhancements, it was demonstrated that PMMA/Bi₂O₃ composites are promising gamma shielding materials. Furthermore, the fast UV curing exerts its great potential in significantly shortening the production cycle of shielding material to enable rapid manufacturing.

• Nuclear Engineering and Technology
• /
• 제52권10호
• /
• pp.2387-2393
• /
• 2020

In this study, a gradient material for shielding neutrons and gamma rays was developed, which consists of epoxy resin, boron carbide (B₄C), lead (Pb) and a little graphene oxide. It aims light weight and compact, which will be applied on the transportable nuclear reactor. The material is made up of sixteen layers, and the thickness and components of each layer were designed by genetic algorithm (GA) combined with Monte Carlo N Particle Transport (MCNP). In the experiment, the viscosities of the epoxy at different temperatures were tested, and the settlement regularity of Pb particles and B₄C particles in the epoxy was simulated by matlab software. The material was manufactured at 25 ℃, the Pb C and O elements of which were also tested, and the result was compared with the outcome of the simulation. Finally, the material's shielding performance was simulated by MCNP and compared with the uniformity material's. The result shows that the shielding performance of gradient material is more effective than that of the uniformity material, and the difference is most noticeable when the materials are 30 cm thick.

• E2M - 전기 전자와 첨단 소재
• /
• 제10권1호
• /
• pp.54-60
• /
• 1997

The electrical and electromagnetic shielding properties have been investigated in polyaniline free standing films with different degrees of elongation cast from N-methyl 2-pyrrolidone(NMP) solution and camphorsulfonic acid(HCSA) doped polyaniline film. The degree of crystallinity of the crosslinked films increased with increasing the draw ratio. For the case of the oriented films doped with hydrochloric acid, we have the values of conductivities up to 173 S/cm. It is considered that the physical micro-crystalline crosslinking domains act as nucleation sites for the increase of relative crystallinity during stretching. We have obtained the value of conductivity 210 S/cm in the HCSA doped polyaniline film cast from the solvent of m-cresol, which is higher than that of the crosslinking oriented films. The electromagnetic shielding efficiency of HCSA doped polyaniline film obtained 37-41 dB in the frequency range of 10MHz-1GHlz, which is higher than that of the crosslinking oriented films. The higher value of electromagnetic shielding efficiency of HCSA doped polyaniline film suggests strong possibility of electromagnetic shielding material.

• 대한방사선기술학회지:방사선기술과학
• /
• 제40권2호
• /
• pp.269-274
• /
• 2017

본 연구에서는 기존의 납을 대체할 수 있는 의료방사선 차폐시트 적용을 위해 몬테카를로 시뮬레이션을 이용하여 각각에 대한 원소별 차폐능을 모의 추정하였다. 원소들의 선정은 차폐성능이 큰 것으로 알려진 원자번호가 큰 원소와 금속원소를 중심으로 최근에는 다양한 복합재들이 차폐성능을 향상시킨다는 보고에 따라 경량화, 가공성, 활동성 등을 고려하여 21개 원소를 선정하였다. 몬테카를로 시뮬레이션 코드를 이용한 전산모사 투과도 실험으로 21개의 원소를 대상으로 시뮬레이션 하여 추정한 결과 납을 대체할 차폐물질로 적당한 원소의 투과율은 텅스텐(w) 98.82％, 가돌리늄(Gd) 92.96％, 주석(Sn) 86.87％, 인듐(In) 86.38％, 안티몬(Sb) 86.33％, 바륨(Ba) 78.51%로 평가되었으며, 각 원소별 차폐성능을 모의 추정한 결과 텅스텐과 금이 98.82%와 98.44%로 차폐율이 가장 높은 것으로 추정되었다. 경제성과 가공성을 고려할 때 위 원소를 화합한 물질로 차폐체를 만드는 것이 적절할 것으로 사료된다.

• 한국융합학회논문지
• /
• 제11권6호
• /
• pp.83-88
• /
• 2020

최근 의료기관에서 친환경 재료로 제작된 방사선 차폐시트를 많이 사용하고 있다. 차폐시트는 폴리머 소재에 차폐물질을 혼입하여 열성형으로 고형적인 형태로 가공된다. 베이스는 수지 계열로 인장강도에는 한계가 있으며, 이를 위해 표면에 부직포 등의 섬유를 합포하여 사용하고 있다. 차폐시트 공정 기술은 차폐성능을 높이고자 차폐물질의 함유량을 높이면 인장강도가 급격히 떨어지는 문제점을 제시하고 있다. 이를 개선하고자 본 연구에서는 차폐시트에 섬유를 Binding하는 방식과 부직포에 소량의 차폐물질인 텅스텐을 함유하여 적층구조로 Laminating방식을 기본 폴리머 형태로 Compression molding방식 세 가지 종류의 차폐시트를 제조하여 동일한 차폐 물질량을 기준으로 차폐성능과 인장 강도를 비교 평가하였다. 세 종류 차폐시트의 비교에서 섬유 코팅 시트와 압착 방식의 시트는 차폐성능 차이는 5%정도이며, 인장강도는 65MPa에서 280MPa로 큰 차이가 나타났다. 적층구조의 차폐시트는 차폐 성능도 차이가 있었으며, 인장강도도 기준의 4배로 증가하였다.

• Nuclear Engineering and Technology
• /
• 제53권1호
• /
• pp.282-293
• /
• 2021

This paper examines gamma-ray shielding properties of SBC-Bx glass system with the chemical composition of 40SiO₂-10B₂O₃-xBaO-(45-x)CaO- yZnO- zMgO (where x = 0, 10, 20, 30, and 35 mol% and y = z = 6 mol%). Mass attenuation coefficient (µ/ρ) which is an essential parameter to study gamma-ray shielding properties was obtained in the photon energy range of 0.015-15 MeV using PHITS Monte Carlo code for the proposed glasses. The obtained results were compared with those calculated by WinXCOM program. Both the values of PHITS code and WinXCOM program were observed in very good agreement. The (µ/ρ values were then used to derive mean free path (MFP), electron density (N_eff), effective atomic number (Z_eff), and half value layer (HVL) for all the glasses involved. Additionally, G-P method was employed to estimate exposure buildup factor (EBF) for each glass in the energy range of 0.015-15 MeV up to penetration depths of 40 mfp. The results reveal that gamma-ray shielding effectiveness of the SBC-Bx glasses evolves with increasing BaO content in the glass sample. Such that SBC-B35 glass has superior shielding capacity against gamma-rays among the studied glasses. Gamma-ray shielding properties of SBC-B35 glass were compared with different conventional shielding materials, commercial glasses, and newly developed HMO glasse. Therefore, the investigated glasses have potential uses in gamma shielding applications.