• Nuclear Engineering and Technology
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• 제52권6호
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• pp.1297-1303
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• 2020

In this study, nuclear radiation shielding and rigidity parameters of Y (0.1-x)B0.6Bi1.8O3La2x glassy system were investigated in order to determine it's suitability for use as nuclear radiation shielding materials. Therefore, a group of bismuth borate glass samples with La₂O₃ additive were synthesized using the technique of melt quenching. According to the results, the increase of the La₂O₃ additive increases the density of the glass samples and the mass attenuation coefficient (μ_m) values, whereas the half-value layer (HVL) and mean free path (MFP) values decrease. The effective atomic number (Z_eff) is also enhanced with an increment of both mass removal cross section for neutron (Σ_R) and absorption neutron scattering cross section (σ_abs). In addition to the other parameters, rigidity parameter values were theoretically examined. The increase of La₂O₃ causes some other important magnitudes to increase. These are the average crosslink density, the number of bonds per unit volume, as well as the stretching force constant values of these glass samples. These results are in concordance with the increase of elastic moduli in terms of the Makishima-Mackenzie model. This model showed an increase in the rigidity of the glass samples as a function of La₂O₃.

• 한국건축시공학회지
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• 제20권2호
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• pp.129-135
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• 2020

핵 및 방사능전 상황에서 방사선에 의한 인명피해를 줄이기 위한 방안으로서 유개호에 자철석이 포함된 중량 콘크리트의 적용 가능성을 확인해보았다. 이에 본 연구에서는 자철광 콘크리트의 방사선 차폐효과를 분석하기 위하여 감마선원을 사용하여 차폐실험을 진행하였고 실험조건과 동일한 몬테칼로 모델링도 하였다. 그 결과 자철광의 함량이 증가할수록 감마선에 대한 차폐효과가 향상됨을 확인할 수 있었다. 향후 자철광 콘크리트가 군사적 목적의 시설물에 적용될 경우 방사선 차폐 측면에서 효과를 얻을 수 있을 것이라 기대한다.

• Nuclear Engineering and Technology
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• 제47권3호
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• pp.380-387
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• 2015

A lead slowing-down spectrometer (LSDS) system is a promising nondestructive assay technique that enables a quantitative measurement of the isotopic contents of major fissile isotopes in spent nuclear fuel and its pyroprocessing counterparts, such as $^{235}U$, $^{239}Pu$, $^{241}Pu$, and, potentially, minor actinides. The LSDS system currently under development at the Korea Atomic Energy Research Institute (Daejeon, Korea) is planned to utilize a high-flux ($>10^{12}n/cm^2{\cdot}s$) neutron source comprised of a high-energy (30 MeV)/high-current (~2 A) electron beam and a heavy metal target, which results in a very intense and complex radiation field for the facility, thus demanding structural shielding to guarantee the safety. Optimization of the structural shielding design was conducted using MCNPX for neutron dose rate evaluation of several representative hypothetical designs. In order to satisfy the construction cost and neutron attenuation capability of the facility, while simultaneously achieving the aimed dose rate limit (< $0.06{\mu}Sv/h$), a few shielding materials [high-density polyethylene (HDPE)eBorax, $B_4C$, and $Li_2CO_3$] were considered for the main neutron absorber layer, which is encapsulated within the double-sided concrete wall. The MCNP simulation indicated that HDPE-Borax is the most efficient among the aforementioned candidate materials, and the combined thickness of the shielding layers should exceed 100 cm to satisfy the dose limit on the outside surface of the shielding wall of the facility when limiting the thickness of the HDPE-Borax intermediate layer to below 5 cm. However, the shielding wall must include the instrumentation and installation holes for the LSDS system. The radiation leakage through the holes was substantially mitigated by adopting a zigzag-shape with concrete covers on both sides. The suggested optimized design of the shielding structure satisfies the dose rate limit and can be used for the construction of a facility in the near future.

• 한국의학물리학회지:의학물리
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• 제26권2호
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• pp.99-105
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• 2015

모니터 전리함은 의료용 선형가속기에서 방출되는 방사선의 세기와 출력 제어를 위하여 사용된다. 본 연구에서는 가속기 기반 방사선 발생장치의 제어 시스템 개발에 사용하기 위하여 모니터 전리함 시작품을 개발하였다. 개발한 모니터 전리함은 평행 평판형 전리함 형태로서 독립적 작동이 가능한 두 개의 전리함으로 구성되어 있으며, 전극의 재료는 방사선의 감쇠를 최소화하기 위하여 얇은 연성인쇄회로기판이 사용되었다. 전리함의 시험을 위하여 코발트-60 방사선원을 이용하여 측정된 전하의 포화특성과 선형성과 같은 선량학적 특성을 평가하였다. 결과적으로 개발된 시작품이 기본 성능을 만족하며 추가 연구의 가능성을 확인하였다.

• 대한방사선치료학회지
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• 제10권1호
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• pp.69-77
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• 1998

When a high energy photon beam is used to treat lesions located in the upper respiratory air passages or in maxillary sinus, the beams often must traverse an air cavity before it reaches the lesion. Because of this traversal of air, it is not clear that the surface layers of the lesion forming the air-tumor tissue interface will be in a state of near electronic equilibrium; if they are not, underdosing of these layers could result. Although dose corrections at large distances beyond an air cavity are accountable by attenuation differences, perturbations at air-tissue interfaces are complex to measure or calculate. This problem has been investigated for 4MV and 10MV X-ray beams which are becoming widely available for radiotherapy with linear accelerator. Markus chamber was used for measurement with variouse air cavity geometries in X-ray beams. Underdosing effects occur at both the distal and proximal air cavity interface. The magnitude depended on geometry, energy, field sizes and distance from the air-tissue interfaces. As the cavity thickness increased, the central axis dose at the distal interface decreased. Increasing field size remedied the underdosing, as did the introduction of lateral walls. Fellowing a $20{\times}2{\times}2\;cm^3$\;air\;cavity,\;4{\times}4\;cm\;field\;there\;was\;an\;11.5\%\;and\;13\%\;underdose\;at\;the\;distal\;interface,\;while\;a\;20{\times}20{\times}2\;cm^3\;air\;cavity\;yielded\;a\;24\%\;and\;29\%$ loss for the 4MV and 10MV beams, respectively. The losses were slightly larger for the 10MV beams. The measurements reported here can be used to guide the development of new calculation models under non-equilibrium conditions. This situation is of clinical concern when lesions such as larynx and maxillary carcinoma beyond air cavities are irradiated.

• 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 ${\frac{E}{AD}}<2MeV{\bullet}cm{\bullet}g^{-1}$.

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.278-284
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• 2023

The synthetic B₂O₃-As₂O₃ glass ceramic are prepared to investigate the physical properties and the radiation shielding capabilities with the variation of concentration of the As₂O₃ with 10, 20, 30, and 40%, respectively. XRD analyses are performed on the fabricated glass-ceramic and depicted the improvement of crystallinity by adding As₂O₃. The radiation shielding properties are studied for the B₂O₃-As₂O₃ glass ceramic. The values of linear attenuation coefficient (LAC) are varied with the variation of incident photon gamma energy (23.1-103 keV). The LAC values enhanced from 12.19 cm^-1-37.75 cm^-1 by raising the As₂O₃ concentration from 10 to 40 mol% at low gamma energy (23.1 keV) for BAs10 and BAs40, respectively. Among the shielding parameters, the half-value layer, transmission factor, and radiation protection efficiency are estimated. Furthermore, the fabricated samples of glass ceramic have low manufacturing costs and good shielding features compared to the previous work. It can be concluded the B₂O₃-As₂O₃ glass ceramic is appropriate to apply in X-ray or low-energy gamma-ray shielding applications.

• 한국음향학회지
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• 제42권3호
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• pp.227-232
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• 2023

수중 소음 공해는 해양 환경에 막대한 영향을 미친다. 본 연구에서는 기포층을 갖는 구조물의 음향 방사 효율을 추정하기 위한 간이 해석법을 제안하였다. 선행 연구 결과를 바탕으로 공기층에 의한 삽입 손실은 감쇠량과 동등하다고 가정하고, 기포층에 의한 삽입 손실은 수치해석 결과의 후처리 기법을 사용하여 계산되었다. 제안된 방법의 검증을 위해 판 구조물에 대한 음향-구조 완전 연성 해석을 수행하였다. 음향-구조 완전 연성 해석은 상용 유한 요소 프로그램 COMSOL Multiphysics를 사용하여 수행되었으며, 기포층의 음향 특성은 Commander 및 Prosperetti 이론을 사용하여 구현하였다. 음향 방사 효율 비교를 통해 간이 해석법과 완전 연성 해석 결과의 경향이 유사함을 확인하였다. 이러한 결과를 바탕으로 기포층을 갖는 쐐기 구조물의 방사 효율 메커니즘을 예측할 수 있음을 확인하였다.

• Nuclear Engineering and Technology
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• 제3권2호
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• pp.65-75
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• 1971

국내에서 산출되는 각종 광물골재를 사용하여 방사선 차폐용 중차폐 콩크리트를 제조하고 감마선에 대한 차폐 효과를 실험한 결과 최적하다고 판단된 자철광 중차폐 콩크리트를 대상으로 60Co 감마선의 Broad beam을 사용하여 방사선 차폐 효과를 측정하였다. 본 실험을 통하여 실험적으로 차폐체내의 방사선의 감쇄곡선으로부터 차폐 체 두께의 변화에 따르는 방사선 투과율과의 상호관계에 관한 수식을 다음과 같이 유도해냈다. I (x) = I (ο) exp(-$\mu$X) exp(1.03$\times$$10^{-1}$X-3.38$\times$$10^{-3}$X$^2$＋5.29$\times$$10^{-5}$X$^3$) X< 20 cm 때, I (x) =I (ο) exp(-$\mu$X) exp(4.66$\times$$10^{-2}$ X＋2.12$\times$$10^{-1}$) X＞20 cm 때. 이와같이 얻은 결과식에서 오른쪽 첫번째항은 최초 감마선의 감쇄를 표시하고 그 다음항은 차폐체 내에서의 감마선 재생계수를 나타낸다. 이 실험에 첨가하여 차폐체의 실제 설계에 입각한 입방형 자철광 구조체 (두께 8 cm, 내부공간 40$\times$40$\times$40cm)에 대한 차폐효과를 측정한 결과 평판 차폐체를 사용할 때 보다 투과 방사선이 증가됨을 알았다.

• Nuclear Engineering and Technology
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• 제55권3호
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• pp.1061-1070
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• 2023

Over the last few years, lead-free inorganic metal perovskites have gained impressive ground in empowering satellites in space exploration owing to their material stability and performance evolution under extreme space environments. The present work has examined the versatility of eight such perovskites as space radiation shielding materials by computing their photon, charged particles and neutron interaction parameters. Photon interaction parameters were calculated for a wide energy range using PAGEX software. The ranges of heavy charged particles (H, He, C, N, O, Ne, Mg, Si and Fe ions) in these perovskites were estimated using SRIM software in the energy range 1 keV-10 GeV, and that of electrons was computed using ESTAR NIST software in the energy range 0.01 MeV-1 GeV. Further, the macroscopic fast neutron removal cross-sections were also calculated to estimate the neutron shielding efficiencies. The examined shielding parameters of the perovskites varied depending on the radiation type and energy. Among the selected perovskites, Cs₂TiI₆ and Ba₂AgIO₆ displayed superior photon attenuation properties. A 3.5 cm thick Ba₂AgIO₆-based shield could reduce the incident radiation intensity to half its initial value, a thickness even lesser than that of Pb-glass. Besides, CsSnBr₃ and La_0.8Ca_0.2Ni_0.5Ti_0.5O₃ displayed the highest and lowest range values, respectively, for all heavy charged particles. Ba₂AgIO₆ showed electron stopping power (on par with Kovar) better than that of other examined materials. Interestingly, La_0.8Ca_0.2Ni_0.5Ti_0.5O₃ demonstrated neutron removal cross-section values greater than that of standard neutron shielding materials - aluminium and polyethylene. On the whole, the present study not only demonstrates the employment prospects of eco-friendly perovskites for shielding space radiations but also suggests future prospects for research in this direction.