• Nuclear Engineering and Technology
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• 제56권2호
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• pp.520-525
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• 2024

The optimization design problem of nuclear reactor radiation shield is a typical multi-objective optimization problem with almost 10 sub-objectives and the sub-objectives are always demanded to be under tolerable limits. In this paper, a design method combining multi-objective optimization algorithms with paralleling discrete ordinate transportation code is developed and applied to shield design of the Savannah nuclear reactor. Three approaches are studied for light-weighted and compact design of radiation shield. Comparing with directly optimization with 10 objectives and the single-objective optimization, the approach by setting sub-objectives representing weight and volume as optimization objectives while treating other sub-objectives as constraints has the best performance, which is more suitable to reactor shield design.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2008년도 추계학술대회B
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• pp.2171-2174
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• 2008

The design of thermal radiation shield cooled by a cryocooler is presented. This study is motivated mainly by our recent development of prototype superconducting magnet system for the Cyclotron K120. The superconducting magnet system is composed of the magnet cryostat, transfer line and supply cryostat. In order to minimize thermal radiation load, the superconducting coil form in the magnet cryostat is enclosed by the thermal radiation shield which is thermally connected to the first-stage cold head of a two-stage cryocooler in the supply cryostat. Since the supply cryostat is located far from the magnet cryostat large temperature gradient along the thermal shield is unavoidable. In this paper, the thermal radiation shield is optimized to minimize temperature gradient with taking into account the cryogenic load, system structure and electrical load. The effect of heat source from thermal conduction through mechanical supports on the temperature distribution of thermal radiation shield is also discussed.

• Journal of Radiation Protection and Research
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• 제32권4호
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• pp.190-193
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• 2007

The objective of this study is to recommend the radiation protection design parameters from the shielding point of view for concrete wall between the decay tank room and the primary pump room in TRIGA Mark-II Research Reactor Facility. The shield design for this concrete wall has been performed with the help of Point-kernel Shielding Code Micro-Shield 5.05 and this design was also validated based on the measured dose rate values with Radiation Survey Meter (G-M Counter) considering the ICRP-60 (1990) recommendations for occupational dose rate limit ($10{\mu}Sv/hr$). The recommended shield design parameters are: (i) thickness of 114.3 cm Ilmenite-Magnetite Concrete (IMC) or 129.54 cm Ordinary Reinforced Concrete (ORC) for concrete wall A (ii) thickness of 66.04 cm Ilmenite-Magnetite Concrete (IMC) or 78.74 cm Ordinary Reinforced Concrete (ORC) for concrete wall B and (iii) door thickness of 3.175 cm Mild Steel (MS) on the entrance of decay tank room. In shielding efficiency analysis, the use of I-M concrete in the design of this concrete wall shows that it reduced the dose rate by a factor of at least 3.52 times approximately compared to ordinary reinforced concrete.

• Journal of Astronomy and Space Sciences
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• 제41권1호
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• pp.17-23
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• 2024

The safety of electronic components used in aerospace systems against cosmic rays is one of the most important requirements in their design and construction (especially satellites). In this work, by calculating the dose caused by proton beams in geostationary Earth orbit (GEO) orbit using the MCNPX Monte Carlo code and the MULLASSIS code, the effect of different structures in the protection of cosmic rays has been evaluated. A multi-layer radiation shield composed of aluminum, water and polyethylene was designed and its performance was compared with shielding made of aluminum alone. The results show that the absorbed dose by the simulated protective layers has increased by 35.3% and 44.1% for two-layer (aluminum, polyethylene) and three-layer (aluminum, water, polyethylene) protection respectively, and it is effective in the protection of electronic components. In addition to that, by replacing the multi-layer shield instead of the conventional aluminum shield, the mass reduction percentage will be 38.88 and 39.69, respectively, for the two-layer and three-layer shield compared to the aluminum shield.

• Nuclear Engineering and Technology
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• 제52권1호
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• pp.178-184
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• 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
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• 제33권4호
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• pp.330-339
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• 2019

Radiant heat shields are normally installed on offshore oil and gas platforms to protect personnel, equipment, and structures from the thermal radiation emitted by a flare system. A heat shield should be individually designed to reduce the thermal radiation to the target level, and then manufactured and installed after the performance verification. However, in general, a heat shield is designed and manufactured by trial and error based on the performance test. For this reason, it is difficult to develop and design radiant heat shields in the Korean shipbuilding and marine equipment industry because of the lack of performance test data and limited experience. In the present study, the results of experiments conducted to verify the performances of radiant heat shields were analyzed, and the thermal radiation characteristics and performance characteristics of the radiant heat shields were investigated. The insights and conclusions developed in the present study will be useful in terms of the design and development of radiant heat shield, as well as in their performance verification tests.

• 대한방사선치료학회지
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• 제27권1호
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• pp.87-95
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• 2015

목 적 : 안와 주변 방사선 치료 시 수정체 피폭선량감소를 위하여 사용된 2차 차폐 block의 유용성을 알아보고자 한다. 대상 및 방법 : Human phantom(Alderson Rando Phantom, The Phantom Laboratory, USA)을 사용하여 CT(Somatom Definition AS, Siemens, Germany) 모의촬영 후 전산화치료계획시스템(Pinnacle, PHILIPS, USA)을 통해 실제 치료와 유사한 IMRT치료계획을 실시하였다. 2차 차폐를 위하여 두께 3mm 지름 25 mm의 납판과 3 mm tungsten eye-shield block(Extra small size, Radiation Products Design, Inc, USA)를 사용하였으며, TPS(Treatment Planning System) 상의 lens dose와 모의치료 상의 lens dose를 OSLD로 측정 비교하였다. 또한, 5 cm 두께의 acrylic phantom에 동일한 조건의 2차 차폐물인 3 mm 납판과 tungsten eye-shield block을 사용하여 200 MU(6 MV, SPD(Source to Phantom Distance)=100 cm, $F{\cdot}S\;5{\times}5cm$)를 조사 및 측정하였으며, 조사야 밖의 누설선 및 투과방사선 영향을 제한시키고자 8 cm 납블럭(O.S.B: Outside Scatter Block)을 적용하여 위와 동일한 실험을 시행하였다. 조사야로부터 1 cm 이격하여 phantom 끝 옆면에 OSLD(Optically Stimulated Luminescence Dosimeter)를 부착하였고, eyelid의 두께에 해당하는 bolus 3 mm를 적용하였다. 결 과 : human phantom을 이용하여 IMRT 치료계획 상의 Lens dose와 실 측정치는 각각 315.9, 216.7 cGy가 측정되었고, 3 mm 납판과 tungsten eye-shield block으로 2차 차폐 후 각각 234.3, 224.1 cGy가 측정되었다. acrylic phantom을 이용한 실험 결과는 no block, 3 mm 납판, tungsten eye-shield block을 사용했을 때 5.24, 5.42, 5.39 cGy가 측정되었으며, 조사야 밖에 O.S.B를 적용하여 no block, 3 mm 납판, tungsten eye-shield block을 실험한 결과 각각 1.79, 2.00, 2.02 cGy가 측정되었다. 결 론 : 광자선 조사 시 critical organ을 보호하기 위하여 2차 차폐를 적용할 시에는 field 외부일지라도 헤드 누설방사선 및 collimator & MLC 투과방사선이 존재하므로 치료부위와 beam 방향에 따라 금속과 같은 높은 원자번호의 차폐물질이 critical organ근처에 있다면 선량 증가의 원인이 될 수 있다는 사실을 알 수 있었다. 따라서 피폭선량 감소를 위한 2차 차폐의 시도는 분명 의미가 있었으나 미 검증된 시도는 오히려 역효과를 가져올 수 있다는 사실을 인지하여 QA를 통해 목적에 부합하는 결과가 나오는지를 사전에 알아보아야 할 것이다.

• 한국항공우주학회지
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• 제34권10호
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• pp.92-98
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• 2006

2006년에 발사된 다목적실용위성은 자세제어 등에 필요한 추력과 모멘트를 발생하기 위해 NASA의 1lbf급 단일추진제 표준 추력기인 MRE-1을 사용하고 있다. 단일추진제 추력기는 추진제와 촉매와의 열분해 반응에 의해 추력을 발생시키는데 이때 발생되는 분해열은 상대적으로 온도가 낮은 주변 구조물 및 전자부품으로 과도한 복사열전달을 발생시키는 열원이 된다. 따라서 추력기와 타 부품 사이에 과도한 복사 열전달을 방지하기 위해서는 복사 열차폐막이 필요하다. 본 논문에서는 열차폐막의 설계/해석 및 제작 등 전반적인 개발 과정에 대해 설명하였다.

• 한국초전도ㆍ저온공학회논문지
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• 제4권2호
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• pp.73-77
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• 2002

In order to derive the detailed design of Thermal Shield Cryopanel. which plays a role to make the Tokamak Nuclear Fusion Equipment work at both static and efficient conditions the commercially available software package FLUENT Version 5.3, was utilized. This study investigated the effects of thermal sources and distributions on the temperatures of Lid. Body. Base. and EH-Port Cryopanel by the numerical technique whose grid generations cover the solid and 9as region of the panel. The physical model of the Thermal Shield Cryopanel is that the 10mm diameter of the pipe with 1mm thickness is soldered on the Stainless steel Panel with 4mm thickness. The heat fluxes to the panel are assumed to be by thermal radiation in the vacuum space and by conduction through the supporters. The inlet conditions of Helium gas are 20 atmospheric Pressures and 60K temperature. The panel shapes with cooling Pipes and the operational conditions to keep appropriate temperature distribution of Thermal Shield Cryopanel Have been found and suggested.

• Nuclear Engineering and Technology
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• 제54권10호
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• pp.3855-3863
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• 2022

An evaluation of the radiation shielding performance of high-Z-particle-loaded polylactic acid (PLA) composite materials was pursued. Specimens were produced via fused deposition modeling (FDM) using copper-PLA, steel-PLA, and BaSO₄-PLA composite filaments containing 82.7, 75.2, and 44.6 wt% particulate phase contents, respectively, and were tested under broad-band flash x-ray conditions at the Sandia National Laboratories HERMES III facility. The experimental results for the mass attenuation coefficients of the composites were found to be in good agreement with GEANT4 simulations carried out using the same exposure conditions and an atomistic mixture as a model for the composite materials. Further simulation studies, focusing on the Cu-PLA composite system, were used to explore a shield design parameter space (in this case, defined by Cu-particle loading and shield areal density) to assess performance under both high-energy photon and electron fluxes over an incident energy range of 0.5-15 MeV. Based on these results, a method is proposed that can assist in the visualization and isolation of shield parameter coordinate sets that optimize performance under targeted radiation characteristics (type, energy). For electron flux shielding, an empirical relationship was found between areal density (AD), electron energy (E), composition and performance. In cases where ${\frac{E}{AD}}{\geq}2MeV{\bullet}cm{\bullet}g^{-1}$, a shield composed of >85 wt% Cu results in optimal performance. In contrast, a shield composed of <10 wt% Cu is anticipated to perform best against electron irradiation when ${\frac{E}{AD}}<2MeV{\bullet}cm{\bullet}g^{-1}$.