• 제목/요약/키워드: Shielding analysis

검색결과 465건 처리시간 0.029초

Simple Calculation Method as a Supplementary Radiation Safety Assessment for Facility with Radiation Generator

  • Kim, Sang-Tae
    • 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.

철근 콘크리트 구조 전자파 차폐 벽체에 대한 성능측정 시스템 연구 (A Study on the Performance Measurement System for the Reinforced Concrete Structure Electromagnetic Shielding Wall)

  • 김보현;조경용;박인욱;오재현;이상훈
    • 한국건설순환자원학회논문집
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    • 제9권4호
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    • pp.492-498
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    • 2021
  • 본 논문에서는 철근 콘크리트 구조 벽체에 대한 전자파 차폐성능 측정시스템을 이용한 전자파 투과율을 분석하였다. 최근 철근 콘크리트 벽체 조건에 대한 전자파 차폐 기술이 연구되고 있으며, 단위 셀 크기의 시험시편에 대한 차폐 성능 시험이 진행되고 있다. 그러나, 단위셀 크기의 시험은 차폐성능 측정범위가 부족하고, 실제 콘크리트 벽체 조건을 반영하기 어렵다는 문제점을 가지고 있다. 이에 대하여 실제 벽체와 유사한 크기와 구조의 2.2m × 2.2m 크기의 대형 벽체 시험시편을 측정할 수 있는 차폐성능 측정 시스템을 구성하였다. 측정 시스템 검증을 위하여 일반 철근 콘크리트 시험시편을 선정하여 실제 차폐성능 측정과 수치해석을 진행하였다. 평가 주파수 범위인 75MHz~2GHz에서 시험결과와 수치해석 결과가 서로 유사한 경향성을 보임이 확인되어 본 차폐성능 측정 시스템이 유효함을 검증하였다.

Radiation Shielding Property of Concrete Using the Rapidly Cooled Steel Slag from Oxidizing Process in the Converter Furnace as Fine Aggregate

  • Kim, Jin-Man;Cho, Sung-Hyun;Kwak, Eun-Gu
    • 한국건축시공학회지
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    • 제12권5호
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    • pp.478-489
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    • 2012
  • Each year, about four million tons of steel slag, a by-product produced during the manufacture of steel by refining pig iron in the converter furnace, is generated. It is difficult to recycle this steel slag as aggregate for concrete because the reaction with water and free-CaO in steel slag results in a volume expansion that leads to cracking. However, the steel slag used in this study is atomized using an air-jet method, which rapidly changes the melting substance at high temperature into a solid at a room temperature and prevents free-CaO from being generated in steel slag. This rapidly-cooled steel slag has a spherical shape and is even heavier than natural aggregate, making it suitable for the aggregate of radiation shielding concrete. This study deals with the radiation shielding property of concrete that uses the rapidly-cooled steel slag from the oxidizing process in the converter furnace as fine aggregate. It was shown that the radiation shielding performance of concrete mixed with rapidly-cooled steel slag is even more superior than that of ordinary concrete.

의료방사선 조영제를 이용한 차폐체 개발; 몬테카를로 시뮬레이션을 통한 황산바륨과 요오드의 차폐능 비교분석 (Development of Shielding using Medical Radiological Contrast Media; Comparison Analysis of Barium Sulfate Iodine Shielding ability by Monte Carlo Simulation)

  • 김선칠
    • 한국방사선학회논문지
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    • 제11권5호
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    • pp.329-334
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    • 2017
  • 본 연구는 의료방사선 차폐를 위해 의료 환경에 적합한 친환경 소재를 찾아 방사선 차폐 시트 제작의 가능성을 추정하고자 하는 것이다. 현재 차폐 소재로 주로 사용되는 납을 대신한 텅스텐 제품이 많이 있으나, 경제성으로 인해 경량의 차폐 시트의 대량생산에는 다소 문제가 있다. 이러한 문제점을 해결하기 위해 경제성 있는 경량 친환경 소재를 필요로 한다. 이러한 소재로써 본 연구에서는 황산바륨과 요오드를 제안하였다. 두 물질은 방사선 촬영에서 이미 조영제로 사용되고 있어 방사선을 흡수하는 특성으로 차폐 재료로써 일정 영역에서 충분히 차폐효과가 있을 것으로 예측하고 있다. 따라서 본 연구에서는 방사선 차폐 재료로 검증하기 위해 몬테카를로 시뮬레이션을 이용하여 모의 추정하였다. 황산바륨과 요오드 등 조영제인 경우 고에너지 영역에서 방사선 흡수효과가 크게 나타나, 의료방사선 고관전압 촬영영역 120 kV의 두께별 에너지영역에서 두 차폐물질의 유효성을 평가하였다. 모의 추정 결과 두 물질 모두 차폐의 유효성을 추정할 수 있었다. 요오드가 황산바륨보다 차폐효과 높았으며, 0.05mm 두께에서는 효과성이 크게 나타났다. 따라서 방사선차폐 시트의 제작 재료로 방사선 조영제인 요오드도 황산바륨과 같이 가능하다는 것을 몬데카를로 시뮬레이션을 통해 확인 할 수 있다.

Design and stress analysis of femur bone implant with composite plates

  • Ramakrishna, S.;Pavani, B.
    • Biomaterials and Biomechanics in Bioengineering
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    • 제5권1호
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    • pp.37-50
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    • 2020
  • Development of lightweight implant plates are important to reduce the stress shielding effect for a prosthesis of femur bone fractures. Stainless steel (SS-316L) is a widely used material for making implants. Stress shielding effect and other issues arise due to the difference in mechanical properties of stainless steel when compared with bone. To overcome these issues, composite materials seem to be a better alternative solution. The comparison is made between two biocompatible composite materials, namely Ti-hydroxyapatite and Ti-polypropylene. "Titanium (Ti)" is fiber material while "hydroxyapatite" and "polypropylene" are matrix materials. These two composites have Young's modulus closer to the bone than stainless steel. Besides the variety of bones, present paper constrained to femur bone analysis only. Being heaviest and longest, the femur is the most likely to fail among all bone failures in human. Modelling of the femur bone, screws, implant and assembly was carried out using CATIA and static analysis was carried out using ANSYS. The femur bone assembly was analyzed for forces during daily activities. Ti-hydroxyapatite and Ti-polypropylene composite implants induced more stress in composite implant plate, results less stress induced in bone leading to a reduction in shielding effect than stainless steel implant plate thus ensuring safety and quick healing for the patient.

CANDU 사용후핵연료 수송용기 방사선차폐 영향평가 (Radiation Shielding Analysis of CANDU Spent Fuel Transport Cask)

  • 최종락;윤정현;강희영;이흥영;정성환
    • Journal of Radiation Protection and Research
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    • 제18권2호
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    • pp.27-35
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    • 1993
  • 중수로형 원자로에서 방출되는 사용후핵연료 다발을 안전하게 운반할 목적으로 CANDU 수송용기에 대한 방사선차폐해석을 수행하였다. 핵연료의 연소도는 7,800MWD/MTU, 냉각기간은 5년으로 하여 ORIGEN2 코드로 방사선원을 구하고 이것으로 핵연료 378다발을 운반할 수 있는 수송용기의 차폐체 두께변화에 따른 선량을 영향을 비교하였다. 계산은 ANISN과 DOT4.2 코드를 사용하였으며, 해석결과 최적의 차폐구조를 선정 하였으며, 또한 IAEA 및 국내 원자력법의 수송법규에 명시된 정상수송 및 가상사고조건에 따른 차폐해석을 수행하여 CANDU 수송용기의 안전성을 입증하였다.

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Neutron Dose Rate Analysis of PWR Spent Fuel Transport Cask Using Monte Carlo Method

  • Do, Mahnsuck;Kim, Jong-Kyung;Yoon, Jeong-Hyoun
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1995년도 추계학술발표회논문집(2)
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    • pp.847-852
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    • 1995
  • A shielding analysis for KSC-7, the shipping cask for transporting the 7 PWR spent fuel assemblies, has been carried out. Radiation source term has been calculated on spent fuel with burnup of 50,000 MWD/MTU and 1.5 years cooling time by ORIGEN2 code. The shielding calculation for the cask has been made by using MCNP4A code with continuous cross section data library from ENDF/B-V. As a result of neutron dose rate analysis, another shielding calculational model on spent fuel shipping cask was provided which is using the Monte Carlo method.

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초전도 공진 코일의 효율성을 높이기 위한 차폐 재질에 따른 무선전력전송 효율비교 분석 (Characteristics of Wireless Power Transmission Using Superconductor Coil to Improve the Efficiency According to the Shielding Materials)

  • 이유경;정인성;황준원;최효상
    • 전기학회논문지
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    • 제65권4호
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    • pp.684-688
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    • 2016
  • The magnetic resonance method requires high quality factor(Q-factor) of resonators. Superconductor coils were used in this study to increase the Q-factor of wireless power transfer(WPT) systems in the magnetic resonance method. The results showed better transfer efficiency compared to copper coils. However, as superconducting coils should be cooled below critical temperatures, they require cooling containers. In this viewpoint, shielding materials for the cooling containers were applied for the analysis of the WPT characteristics. The shielding materials were applied at both ends of the transmitter and receiver coils. Iron, aluminum, and plastic were used for shielding. The electric field distribution and S-parameters (S11, S21) of superconducting coils were compared and analyzed according to the shield materials. As a result, plastic shielding showed better transfer efficiency, while iron and aluminum had less efficiency. Also, the maximum magnetic field distribution of the coils according to the shielding materials was analyzed. It was found that plastic shielding had 5 times bigger power transfer rate than iron or aluminum. It is suggested that the reliability of superconducting WPT systems can be secured if plastic is used for the cooling containers of superconducting resonance coils.

X-ray/gamma radiation shielding properties of Aluminium-Bariume-Zinc Oxide nanoparticles synthesized via low temperature solution combustion method

  • K.V. Sathish;K.N. Sridhar;L. Seenappa;H.C. Manjunatha;Y.S. Vidya;B. Chinnappa Reddy;S. Manjunatha;A.N. Santhosh;R. Munirathnam;Alfred Cecil Raj;P.S. Damodara Gupta;B.M. Sankarshan
    • Nuclear Engineering and Technology
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    • 제55권5호
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    • pp.1519-1526
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    • 2023
  • For the first time Aluminium-BariumeZinc oxide nanocomposite (ZABONC) was synthesized by solution combustion method where calcination was carried out at low temperatures (600℃) to study the electromagnetic (EM) (X/γ) radiation shielding properties. Further for characterization purpose standard techniques like PXRD, SEM, UV-VISIBLE, FTIR were used to find phase purity, functional groups, surface morphology, and to do structural analysis and energy band gap determination. The PXRD pattern shows (hkl) planes corresponding to spinel cubic phase of ZnAl2O4, cubic Ba(NO3)2, α and γ phase of Al2O3 which clearly confirms the formation of complex nano composite. From SEM histogram mean size of nano particles was calculated and is in the order of 17 nm. Wood and Tauc's relation direct energy band gap calculation gives energy gap of 2.9 eV. In addition, EM (X/γ) shielding properties were measured and compared with the theoretical ones using standard procedures (NaI (Tl) detector and multi channel analyzer MCA). For energy above 356 keV the measured shielding parameters agree well with the theory, while below this value slight deviation is observed, due to the influence of atomic/crystallite size of the ZABONC. Hence synthesized ZABONC can be used as a shielding material in EM (X/γ) radiation shielding.

Radiation attenuation and elemental composition of locally available ceramic tiles as potential radiation shielding materials for diagnostic X-ray rooms

  • Mohd Aizuddin Zakaria;Mohammad Khairul Azhar Abdul Razab;Mohd Zulfadli Adenan;Muhammad Zabidi Ahmad;Suffian Mohamad Tajudin;Damilola Oluwafemi Samson;Mohd Zahri Abdul Aziz
    • Nuclear Engineering and Technology
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    • 제56권1호
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    • pp.301-308
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    • 2024
  • Ceramic materials are being explored as alternatives to toxic lead sheets for radiation shielding due to their favorable properties like durability, thermal stability, and aesthetic appeal. However, crafting effective ceramics for radiation shielding entails complex processes, raising production costs. To investigate local viability, this study evaluated Malaysian ceramic tiles for shielding in diagnostic X-ray rooms. Different ceramics in terms of density and thickness were selected from local manufacturers. Energy Dispersive X-ray Fluorescence (EDXRF) and X-ray Fluorescence (XRF) characterized ceramic compositions, while Monte Carlo Particle and Heavy Ion Transport code System (MC PHITS) simulations determined Linear Attenuation Coefficient (LAC), Half-value Layer (HVL), Mass Attenuation Coefficient (MAC), and Mean Free Path (MFP) within the 40-150 kV energy range. Comparative analysis between MC PHITS simulations and real setups was conducted. The C3-S9 ceramic sample, known for homogeneous full-color structure, showcased superior shielding attributes, attributed to its high density and iron content. Notably, energy levels considerably impacted radiation penetration. Overall, C3-S9 demonstrated strong shielding performance, underlining Malaysia's potential ceramic tile resources for X-ray room radiation shielding.