• Title/Summary/Keyword: 차폐법

Search Result 154, Processing Time 0.023 seconds

Assessment of Spatial Dose Distribution in the Diagnostic Imaging Laboratory by Monte Carlo Simulation (몬테카를로 전산해석에 의한 X선 실습실의 공간선량분포 평가)

  • Cho, Yun-Hyeong;Kang, Bo Sun
    • Journal of the Korean Society of Radiology
    • /
    • v.11 no.6
    • /
    • pp.423-428
    • /
    • 2017
  • In this study, the calculation of the effective spatial dose distribution of the diagnostic imaging laboratory of K university was performed by the Monte Carlo simulation. The radiation generator has a maximum tube voltage of 150 kVp and a maximum current of 700 mA. Using the results, we compared the spatial effective dose distributions of diagnostic imaging laboratory when the shielding door was closed and opened. In conclusion, it was found that the effective dose in the operating room of the diagnostic imaging laboratory does not exceed the annual dose limit (6 mSv/y) of the student (occasional visitor) even when the door is opened. However, since the effective dose when the door is open is about 16 times higher in front of the lead glass window and about 3,000 times higher in front of the doorway than the case when the door is closed, closing the shielding door at the time of the practical exercising reduces unnecessary radiation exposure by great extent.

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

  • Choi, Jong-Rak;Yoon, Jung-Hyun;Kang, Hee-Young;Lee, Heung-Young;Chung, Sung-Whan
    • Journal of Radiation Protection and Research
    • /
    • v.18 no.2
    • /
    • pp.27-35
    • /
    • 1993
  • A shielding analysis of the shipping cask for transporting the CANDU spent fuel bundles has been studied. Radiation source term has been calculated on spent fuel with burn-up of 7,800 MWD/MTU and 5 years cooling time by ORIGEN2 code. The shielding calculation for the cask capable of transporting 378 bundles of CANDU spent fuel has been made by use of 1-D ANISN and 2-D DOT 4.2 codes. As a result of analysis, the optimum shield thickness of cask was obtained. And it is proved that the safety in radiation shielding under normal transport and hypothetical accident conditions is confirmed to satisfy the allowable values specified in IAEA Safety Series No. 6 and the Korean Atomic Law.

  • PDF

Probability-Based Performance Prediction of the Nuclear Contaminated Bio-Logical Shield Concrete Walls (원전 방사화 콘크리트 차폐벽의 확률 기반 성능변화 예측)

  • Kwon, Ki-Hyon;Kim, Do-Gyeum;Lee, Ho-Jae;Seo, Eun-A;Lee, Jang-Hwa
    • Journal of the Korean Recycled Construction Resources Institute
    • /
    • v.7 no.4
    • /
    • pp.316-322
    • /
    • 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.

Neutron Shielding Analysis for a Spent Fuel Container Using XSDRN, ONEDANT and MCNP Codes (XSDRN, ONEDANT및 MCNP에 의한 사용후 핵연료 용기의 중성자 차폐 해석)

  • Kim, Kyo-Youn;Lee, Tae-Young;Ha, Chung-Woo;Kim, Jong-Kyung
    • Journal of Radiation Protection and Research
    • /
    • v.14 no.1
    • /
    • pp.46-55
    • /
    • 1989
  • Neutron shielding for a spent fuel container was analized using the Monte Carlo code MCNP coupled with discrete ordinates codes, XSDRN and ONEDANT. The ORIGEN-S code was used to determine the fixed neutron source, and the spectral source information for MCNP were obtained from a 10 group XSDRN calculation and a 27 group ONEDANT calculation. When the depleted uranium shield was used, the results from ONEDANT and XSDRN calculations agreed with the MCNP results within 10% and 20%, respectively. Depleted uranium appears more effective than lead or steel as a neutron shield.

  • PDF

Shielding Calculations of Accelerator Facility for Medical Isotope Production using MCNPX Code (MCNPX 코드를 이용한 의료용 방사성동위원소 생산을 위한 가속기 시설의 방사선차폐 및 선량 계산)

  • Seo Kyu-Seok;Kim Chan-Hyeong
    • Progress in Medical Physics
    • /
    • v.15 no.4
    • /
    • pp.210-214
    • /
    • 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.

  • PDF

A Vibration Mode Analysis of Resilient Mounting System and Foundation Structure of Acoustic Enclosure using Finite Element Method (유한요소법을 이용한 음향차폐장치용 탄성마운트 시스템 및 받침대의 진동모드 해석)

  • 정우진;배수룡;함일배
    • Journal of KSNVE
    • /
    • v.9 no.3
    • /
    • pp.493-501
    • /
    • 1999
  • The vibration modes of resilient mounting system and foundation structure which support diesel engine/generator set and acoustic enclosure walls play an important role in the vibration transmission process. So, it is necessary to perform vibration mode analysis of resilient mounting system and foundation structure. For some reasons, if the vibration modal analysis of resilient mounting system and foundation structure of acoustic enclosure could be simultaneously done by finite element method, it would be very efficient approach. In this paper, vibration modal analysis method using finite element method for multi stage mounting system having n d.o.f model was proposed. Vibration analysis of single and double stage resilient mounting system was performed to verify the validity of the proposed method. Also frequency response results were compared in case of rigid foundation model and finite element foundation model which was compared with experimental modal analysis results.

  • PDF

Electromagnetic Interference Shielding Behaviors of Electroless Nickel-loaded Carbon Fibers-reinforced Epoxy Matrix Composites (무전해 니켈도금된 탄소섬유강화 에폭시기지 복합재료의 전자파 차폐특성)

  • Hong, Myung-Sun;Bae, Kyong-Min;Lee, Hae-Seong;Park, Soo-Jin;An, Kay-Hyeok;Kang, Shin-Jae;Kim, Byung-Joo
    • Applied Chemistry for Engineering
    • /
    • v.22 no.6
    • /
    • pp.672-678
    • /
    • 2011
  • In this work, carbon fibers were electrolessly Ni-plated in order to investigate the effect of metal plating on the electromagnetic shielding effectiveness (EMI-SE) of Ni-coated carbon fibers-reinforced epoxy matrix composites. The surfaces of carbon fibers were characterized by scanning electron microscopy (SEM) and X-ray photoelectron spectroscopy (XPS). Electric resistance of the composites was tested using a 4-point-probe electric resistivity tester. The EMI-SE of the composites was evaluated by means of the reflection and adsorption methods. From the results, it was found that the EMI-SE of the composites enhanced with increasing Ni plating time and content. In high frequency region, the EMI-SE didn't show further increasing with high Ni content (Ni-CF 10 min) compared to the Ni-CF 5 min sample. In conclusion, Ni content on the carbon fibers can be a key factor to determine the EMI-SE of the composites, but there can be an optimized metal content at a specific electromagnetic frequency region in this system.

Comparison of Thyroid Doses for Shielding Material Changes in Neck Computed Tomography (Neck CT에서 차폐체 재료 변화에 따른 Thyroid 선량 비교 연구)

  • Kang, Eun Bo
    • Journal of the Korean Society of Radiology
    • /
    • v.13 no.1
    • /
    • pp.65-71
    • /
    • 2019
  • With regard to current Neck CT, Bismuth shielding boards are often being used to reduce exposure to superficial organs such as the thyroid. However, beam hardening often occurs near superficial organs with Bismuth shielding boards and variations in CT Number, Noise, and Uniformity values occur severely. This study looked into the usefulness of shielding boards made from aluminum and silicone that can be easily obtained and have good machinability by comparing them to the existing Bismuth shielding board. An Aluminum 7.3mm and a Silicone 21.5mm were made with shielding ratios similar to that of the Bismuth(0.06 mmPb). TLD (TLD-100) was placed on the thyroid area of the Phantom (RS-108T) and 5 doses were measured for each. To compare image quality, CT Number and Noise variations in axial images of the thyroid area in Neck CT images were compared. Also, variations in CT Number, Noise, and Uniformity were measured in the AAPM phantom images and compared. In the results, when thyroid doses for each shielding board were compared, the Bismuth shielding board showed a 14% reduction, the Silicone 21.5mm showed a 15% reduction, and the Aluminum 7.3mm showed a 13% reduction compared to the Non-Shield. Statistically, there were no significant differences in comparison with the Bismuth shielding board. In CT Number variations of thyroid area images, variations were largest for the Bismuth shielding board. With Uniformity evaluations of the AAPM phantom, the Bismuth shielding board was found unsuitable and the Aluminum 7.3mm and Silicone 21.5mm satisfied the acceptance criteria. Research results show that the Aluminum 7.3mm and Silicone 21.5mm have a similar shielding ratio to the high-priced Bismuth shielding board that is currently being used clinically and in comparison tests of CT Number attenuation coefficient variations, Noise, and Uniformity which are phantom image evaluation items, they proved to be better than Bismuth shielding boards. If various shielding boards are made using aluminum and silicone, sized appropriately for superficial organs, it would be useful in decreasing patient doses.