• Journal of Radiation Protection and Research
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• 제48권3호
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• pp.162-166
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• 2023

Background: Assessment of the radiation doses to which workers are exposed can differ depending on the placement of dosimeters on the body. In addition, it is affected by whether the placement is under or over a shielding apron. This study aimed to evaluate the actual positioning of personal dosimeters on the body, with or without shielding aprons, among radiation workers in Korea. Materials and Methods: We analyzed the survey data, which included demographic characteristics, such as sex, age, occupation, work history, and placement of the personal dosimeter being worn, from a cohort study of Korean radiation workers. We assessed the use of personal dosimeters among workers, stratified by sex, age, working period, starting year of work, and occupation. Results and Discussion: Overall, high compliance (89.1% to 99.0%) with the wearing of dosimeters on the chest was observed regardless of workers' characteristics, such as age, sex, occupation, and work history. However, the placement of dosimeters, either under or over the shielding aprons, was inconsistent. Overall, 40.1% of workers wore dosimeters under their aprons, while the others wore dosimeters over their aprons. This inconsistency indicates that radiation doses are possibly measured differently under the same exposure conditions solely owing to variations in the placement of worn dosimeters. Conclusion: Although a lack of uniformity in dosimeter placement when wearing a shielding apron may not cause serious harm in radiation dose management for workers, the development of detailed guidelines for dosimeter placement may improve the accuracy of dose assessment.

• 한국방사선학회논문지
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• 제14권6호
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• pp.733-740
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• 2020

의료종사자의 피폭선량을 줄이기 위한 최근 연구에서, 방사선이 산란될 때 발생하는 광전효과를 이용하여 방사선치료실 입구에서의 선량을 줄이는 방법이 제안되었다. 이 방법은 특히 저에너지 광자에 효과적이기 때문에 본 연구에서는 몬테카를로 시뮬레이션을 이용하여 슬릿형태 구조물의 일반촬영실 산란 엑스선에 대한 차폐성능을 평가하였다. 두께 2 mm, 폭 50 mm, 길이 900 mm인 판을 2 mm 간격으로 수평 적재하는 형태의 슬릿형태 구조물은 알루미늄에 비해 철 또는 납으로 만드는 경우 차폐효과가 뛰어났다. 재질을 철로 한정한 경우 선원과 관심구역 사이에서 결정된 구조물의 설치위치는 차폐효과와 무관했으며, 판의 폭은 차폐효과에 비례했다. 폭 50 mm 철판을 사용한 경우 산란선이 직접 발생하는 바닥 및 환자의 높이를 제외하면 약 99.9% 또는 그 이상의 차폐효과가 있었다.

• Nuclear Engineering and Technology
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• 제55권6호
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• pp.2215-2221
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• 2023

In order to further meet the requirements of weight, volume, and dose minimization for new nuclear energy devices, the bare-bones multi-objective particle swarm optimization algorithm is used to automatically and iteratively optimize the design parameters of radiation shielding system material, thickness, and structure. The radiation shielding optimization program based on the bare-bones particle swarm optimization algorithm is developed and coupled into the reactor radiation shielding multi-objective intelligent optimization platform, and the code is verified by using the Savannah benchmark model. The material type and thickness of Savannah model were optimized by using the BBMOPSO algorithm to call the dose calculation code, the integrated optimized data showed that the weight decreased by 78.77%, the volume decreased by 23.10% and the dose rate decreased by 72.41% compared with the initial solution. The results show that the method can get the best radiation shielding solution that meets a lot of different goals. This shows that the method is both effective and feasible, and it makes up for the lack of manual optimization.

• 대한방사선치료학회지
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• 제2권1호
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• pp.31-40
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• 1987

In the case of designing a high dose rate remote controlled afterloading treatment room with existing hospital facilities. We must construct the effective protective barriers so as to reduce the primary and scattered radiation up to the maximum permissible dose level. It is difficult to reinforce the barrier thickness of the shielding requirements because of the limited space and the problem of the existing building structure at the surrounding area. Therefore we can reduce the intensity of primary radiation to the required degree at the location of interest with installing the appropriate I shaped Pb barriers between the radiation source and the shielding wall of the concrete. As a result, it was possible to reduce the intensity of the primary radiation below the M.P.D level by using additional Pb barriers instead of increasing thickness of concrete wall.

• 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.

• 한국방사선학회논문지
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• 제17권3호
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• pp.449-457
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• 2023

방사선 감수성이 높은 부위의 방사선 검사 시 피폭선량 감소를 위해 사용하는 차폐체가 조사야에 포함될 경우 방사선 영상에서 밝게 표현되며 영상 정보의 손실이 발생한다. 영상 정보의 손실은 진단과 치료에 제한점을 주며 재촬영이 필요할 경우, 불필요한 방사선에 노출될 수 있다. 본 논문에서는 수용성 요오드 조영제와 물을 혼합한 다양한 농도의 차폐체를 제작하여 영상 손실을 최소화하면서 기존 차폐체와 동등한 차폐 효과를 발생하는 방사성 방호 차폐체를 연구하고자 하였다. 차폐체는 물 100 ml, 수용성 요오드 조영제 100 ml, 수용성 요오드 조영제와 물을 20 : 80, 40 : 60, 60 : 40, 80 : 20 비율로 각각 100 ml를 제작했다. 차폐 효율을 측정하기 위해서 차폐체를 가로 9.5 cm, 세로 9.5cm의 플라스틱 용기에 약 1.5 cm 높이로 담고 흡수선량 감쇠율을 평가하였다. 조사 조건은 골반 촬영 조건을 기준으로 5회 반복 측정하였고 측정한 조사선량 값을 흡수선량 값으로 변환한 뒤 평균값을 산출 비교하였다. 영상 정보 손실 정도는 팬텀의 골반강 부위를 차폐하고 획득한 영상을 근골격 전문의 2명과 방사선사 8명이 주요 해부학적 구조물의 관찰 정도를 평가 후 선택하였다. 또한 차폐한 부위의 영상에서 표현되는 골격과 가스의 신호 강도 차이를 분석한 결과 방사선 감쇠 효율성은 수용성 요오드 조영제의 비율이 높을수록 높은 차폐 효율을 나타냈다. 영상 정보의 손실 평가에서 평가자들은 수용성 요오드 조영제 20 ml 혼합물에서 해부학적 구조물의 관찰이 용이하다 평가하였으며 60 ml 이상의 혼합물에서는 구조물의 관찰이 불가능하였다. 골격과 가스의 신호강도 차이는 p < 0.001로 평균값의 차이가 유의미한 차이가 있었으며, 조영제의 농도가 높을수록 신호 강도의 차이는 적었다. 수용성 요오드 조영제 차폐체는 방사선 감쇠 효율이 기존의 차폐체 보다 떨어지지만, 차폐체가 관찰하는 목적부위 이거나 가까이 위치하여 차폐체를 적용하지 못하는 경우에 사용한다면, 영상 손실을 최소화하며 보다 더 적극적인 방사선 방호의 역할을 수행할 수 있다.

• 대한방사선기술학회지:방사선기술과학
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• 제3권1호
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• pp.67-72
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• 1980

To shield the radiation, we can make use of various materials, but the scattered rays can be caused by the shielding materials. The degree of the scattered rays production is influenced by the nature of the shielding materials and the energy of the radiation, therefore to choose the proper shielding material is the most important matter in radiation protection. Authors made an experimental study on the scattered rays generated from the shielding materials, and obtained the results as follows: 1. In the ranking of the scattered rays production: Cement bricks, black colored fire bricks, and red colored fire bricks were marked the first the second, and the third ranking respectly, and the last order was lead plates. 2. In the relative ranking of the scattered rays production by energy increase: Lead plates were marked the first order, the next and third order were red colored fire bricks and black colored fire bricks respectly, and cement bricks were marked the last order. 3. The scattered ray ratio of lateral-back point per lateral point were generally decreased by energy increment. The diminishing orders were that lead plates were the first order, and the next and the third order were red colored fire bricks and black colored fire bricks respectly, cement bricks were marked the last order.

• Nuclear Engineering and Technology
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• 제54권4호
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• pp.1456-1463
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• 2022

The aim of this work is to study the radiation shielding properties of cement samples with waste glass incortated into its composition. The mass attenuation coefficient (MAC) of the samples were experimentally determined to evaluate their radiation shielding ability. The experimental coefficient was evaluated using NaI detector for gamma energies between 59.53 keV and 1408.01 keV using different radioactive point sources Am-241, Eu-152, Co-60, and Cs-137, and the gamma transmission parameters half-value layer, mean free path, and transmission factor were calculated. The theoretical coefficient of the composites was determined using Geant4 and XCOM software. The results were also compared against Geant4 and XCOM simulations by calculating the relative deviation between the values to determine the accuracy of the results. In addition the mechanical properties (including Compressive and porosity) as well as the thermogravimetric analysis were tested for the present samples. Overall, it was concluded that the cement sample with 50% waste glass has the greatest shielding potential for radiation shielding applications and is a useful way to reuse waste glass.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1885-1891
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• 2023

The present work aims to fabricate Na_1+xZr₂Si_xP_3-xO₁₂ compound at various calcination temperatures based on the zircon mineral. The fabricated compound was calcinated at 250, 500, and 1000℃. The effect of calcination temperature on the structure, crystal phase, and radiation shielding properties was studied for the fabricated compound. The X-ray diffraction diffractometer demonstrates that, the monoclinic crystal phase appeared at a calcination temperature of 250℃ and 500℃ is totally transformed to a high-symmetry hexagonal crystal phase under a calcination temperature of 1000℃. The radiation shielding capacity was also qualified for the fabricated compounds using the Monte Carlo N-Particle transport code in the g-photons energy interval between 15keV and 122keV. The impacts of calcination temperature on the g-ray shielding behavior were clarified in the present study, where the linear attenuation coefficient was enhanced by 218% at energy of 122keV, when the calcination temperature increased from 250 to 1000℃, respectively.

• Journal of Radiation Protection and Research
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• 제40권2호
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• pp.92-100
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• 2015

경수로 사용후핵연료 건식 중간저장시설의 방사선영향평가 효율성 개선을 목적으로 '선원항 지정방법에 따른 민감도 평가', '2-Step 계산'기법 개발 및 '냉각기간 이득효과' 적용에 따른 방사선 영향평가를 수행하였다. 본 연구에서는 저장건물의 용기배열 순서에 따라 순차적으로 선원항을 지정하여 직접선량에 미치는 민감도를 평가하였으며, 차폐건물 외벽에서의 방사선량은 내벽과 인접한 최근접 2개 열에 의한 영향이 지배적임을 확인하였다. 또한, 저장시설에 차폐 건물이 도입될 경우, 막대한 전산해석 시간을 감소시키기 위해 '2-Step 계산'기법을 수립하여 평가한 결과는 절반가량의 해석시간으로 직접(1-Step) 계산결과와 유사한 결과를 도출하였다. 마지막으로, 저장시설에 순차적으로 저장되는 저장용기의 보관기간을 사용후핵연료의 실제 냉각기간을 적용하면 건물 외벽에서의 방사선량이 냉각기간을 모두 동일하게 설정한 계산값에 비해 40% 정도 낮게 평가됨을 확인하였다. 본 연구는 중간저장시설의 방사선 영향평가를 위한 몬테칼로 차폐해석 방법의 효율성을 향상시키고자 수행되었으며, 좀 더 다양한 사례에 대한 평가를 통하여 신뢰성을 향상시킨다면 저장시설의 설계 및 부지경계 기준설정에 활용할 수 있을 것이다.