Radiation Shielding Effects of Tungsten and Boron Carbide Coating Materials Fabricated by HVOF Techniuqe

Beom Kyu Kim,Seung Heon Baek,Geun Dong Song,Yeong Ho Son,Jae Hun Lee,Young Jin Kim 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.2

This study focuses on the development of coatings designed for storage containers used in the management of radioactive waste. The primary objective is to enhance the shielding performance of these containers against either gamma or neutron radiation. Shielding against these types of radiation is essential to ensure the safety of personnel and the environment. In this study, tungsten and boron cabide coating specimens were manufactured using the HVOF (High-Velocity Oxy Fuel) technuqe. These coatings act as an additional layer of protection for the storage containers, effectively absorbing and attenuating gamma and neutron radiation. The fabricated tungsten and boron carbide coating specimens were evaluated using two different testing methods. The first experiment evaluates the effectiveness of a radiation shielding coating on cold-rolled steel surfaces, achieved by applying a mixture of WC (Tungsten Carbide) powders. WC-based coating specimens, featuring different ratios, were prepared and preliminarily assessed for their radiation shielding capabilities. In the gamma-ray shielding test, Cs-137 was utilized as the radiation source. The coating thickness remained constant at 250 μm. Based on the test results, the attenuation ratio and shielding rate for each coated specimen were calculated. It was observed that the gammaray shielding rate exhibited relatively higher shielding performance as the WC content increased. This observation aligns with our findings from the gamma-ray shielding test and underscores the potential benefits of increasing the tungsten content in the coating. In the second experiment, a neutron shielding material was created by applying a 100 μm-thick layer of B4C (Boron Carbide) onto 316SS. The thermal neutron (AmBe) shielding test results demonstrated an approximate shielding rate of 27%. The thermal neutron shielding rate was confirmed to exceed 99.9% in the 1.5 cm thick SiC+B4C bulk plate. This indicates a significant reduction in required volume. This study establishes that these coatings enhance the gamma-ray and neutron shielding effectiveness of storage containers designed for managing radioactive waste. In the future, we plan to conduct a comparative evaluation of the radiation shielding properties to optimize the coating conditions and ensure optimal shielding effectiveness.

롤투롤 스퍼터링 증착을 통한 납(Pb) 대체용 방사선 차폐필름 개발

김성헌,변정섭,지영빈 한국방사선학회 2023 한국방사선학회 논문지 Vol.17 No.3

Lead(Pb), which is currently mainly used for shielding purposes in the medical radiation, has excellent radiation shielding functions, but is continuously exposed to radiation directly or indirectly due to the harmfulness of lead itself to the human body and the inconvenience caused by its heavy weight. Research on shielding materials that are human-friendly, lightweight, and convenient to use that can block risks and replace lead is continuously being conducted. In this study, based on the commonly used polyethylene terephthalate (PET) film and the fabric material used in actual radiation protective clothing, a multi-layer thin film was realized through sputtering and vacuum deposition of bismuth, tungsten, and tin, which are metal materials that can shield radiation. Thus, a shielding film was produced and its applicability as a radiation shielding material was evaluated. The radiation shielding film was manufactured by establishing the optimized conditions for each shielding material while controlling the applied voltage, roll driving speed, and gas supply amount to manufacture the shielding film. The adhesion between the parent material and the shielding metal thin film was confirmed by Cross-cut 100/100, and the stability of the thin film was confirmed through a hot water test for 1 hour to measure the change of the thin film over time. The shielding performance of the finally realized shielding film was measured by the Korea association for radiation application (KARA), and the test conditions (inverse wide beam, tube voltage 50 kV, half layer 1.828 mmAl) were set to obtain an attenuation ratio of 16.4 (initial value 0.300 mGy/s, measured value 0.018 mGy/s) and damping ratio 4.31 (initial value 0.300 mGy/s, measured value 0.069 mGy/s) were obtained. by securing process efficiency for future commercialization, light and shielding films and fabrics were used to lay the foundation for the application of films to radiation protective clothing or construction materials with shielding functions. 현재 의료방사선 분야에서 차폐를 목적으로 주로 사용되고 있는 납(Pb)소재는 방사선 차폐 기능은 뛰어나지만 납 자체가 가지고 있는 인체 유해성과 무거운 무게에 의한 불편함 때문에 지속적으로 직, 간접적으로 방사선 피폭 위험을 차단함과 동시에 납 소재를 대체할 수 있는 인체 친화적인이며 가벼우면서 사용편의성을 가진 차폐소재의 연구는 지속적으로 진행되어지고 있다. 본 연구에서는 일반적으로 사용되는 PET (polyethylene terephthalate) 필름과 실제 방사선 방호복 사용되는 원단소재를 기재로 하여 방사선을 차폐할 수 있는 금속물질인 비스무트, 텅스텐, 주석을 스퍼터링 진공증착 방식을 통한 다층박막을 구현하여 차페 필름을 제작하여 방사선 차폐소재로의 적용가능성을 평가하였다. 차폐필름을 제작하기 위한 인가전압, 롤 구동속력, 가스공급량을 제어하면서 차폐물질별 최적화된 조건을 확립하여 방사선 차폐필름 제작하였다. 모재와 차폐금속박막간 밀착력 확인은 Cross-cut 100/100으로 확인하였고 시간에 따른 박막의 변화를 측정하기 위해 내열탕 테스트 1시간을 통하여 박막의 안정성을 확인하였다. 최종적으로 구현된 차폐필름의 차폐성능은 한국방사선진흥협회를 통한 실제 방사선 차폐성능을 측정한 결과 시험조건(역넓은 빔, 관전압 50 kV, 반가층 1.828 mmAl)을 설정하여 감쇠비 16.4 (초기값 0.300 mGy/s, 측정값 0.018 mGy/s)와 감쇠비 4.31 (초기값 0.300 mGy/s, 측정값 0.069 mGy/s)의 결과를 얻었다. 추후 제품화를 위한 공정효율성을 확보하여 가벼우면서 차폐성능을 보유한 필름 및 원단을 활용하여 방사선 방호복이나 차폐기능을 가진 건축자재로의 필름적용을 위한 초석을 마련하였다.

폴리 염화 비닐(PVC)의 저선량 융합 방사선에너지에 대한 차폐 효과 평가

김선칠,조성현 한국융합학회 2019 한국융합학회논문지 Vol.10 No.12

PVC was chosen as a plastic product that can cope with lead, a radiation shielding material that is widely used in medical institutions. In addition to radiation shielding clothing, we want to evaluate whether it can be used as a medical device component and industrial shielding material in low dose areas. Commercial PVC has a density of 3.68 g/㎠ and can be positively expected sufficient shielding effect in certain radiation areas such as material flexibility and economy efficiency, and can be transformed into various forms and used as a lightweight shielding wall. The shielding performance was tested by adjusting the thickness of 5 sheets of 3mm PVC in the range of medical radiation used for clinical examination in medical institutions. Shielding performance against effective energy was evaluated based on tube radiation voltage of medical radiation. The thicker the PVC, the lower the tube voltage and the lower the effective energy, the greater the shielding effect. The shielding effect was 70% at 12mm thickness and 80kVp tube voltage. Therefore, the shielding effect of PVC material has a high dependence of thickness. In the future, continuous research is needed to make thin and light eco-friendly products while improving shielding performance. 의료기관에서 많이 사용되는 방사선 차폐 재료인 납을 대처할 수 있는 플라스틱 제품으로 PVC를 선택하였다. 방사선 차폐 의복 이외에 저선량 영역에서 의료기기 부품, 산업용 차폐 재료로 사용이 가능한지 평가하고자 한다. 상업용 PVC는 밀도가 3.68 g/㎠ 으로 재료의 유연성과 경제성 등 일정 방사선 영역에서는 충분한 차폐 효과를 긍정적으로 기대할 수 있으며, 다양한 형태로 변형이 가능하고, 경량의 차폐벽으로 사용할 수 있다. 의료기관에서 임상 검사 시 사용되는 의료방사선 영역 대에서 3mm PVC 5장을 두께로 조절하여 차폐 성능을 실험하였다. 의료방사선의 관전압 기준으로 실효에너지에 대한 차폐 성능을 평가하였다. PVC는 두께가 두꺼울수록 관전압과 실효에너지가 낮을수록 차폐효과는 크게 나타났으며, 차폐효과는 12mm 두께에 관전압 80kVp에서 70%의 차폐효과가 있었다. 따라서 PVC 재료의 차폐효과는 두께의 의존율이 높게 나타났다. 앞으로는 차폐 성능을 높이면서 얇고 가벼운 친환경 제품을 만들기 위한 지속적인 연구가 필요하다.

방사선 차폐체 제작을 통한 작업종사자 피폭 감소 방안

김기,홍건철,곽인석,박선명,최춘기,석재동,Kim, Ki,Hong, Gun-Chul,Kwak, In-Suk,Park, Sun-Myung,Choi, Choon-Ki,Seok, Jae-Dong 대한핵의학기술학회 2010 핵의학 기술 Vol.14 No.2

PET/CT 기기의 발달과 대중화에 따라 검사 건수도 꾸준히 증가하고 있다. 이는 방사선 작업종사자의 피폭 선량도 함께 증가시키는 결과를 초래한다. 본 연구에서는 방사선 차폐체를 제작하여 방사선 작업종사자의 피폭 감소를 확인하고 또한 작업종사자의 업무 만족도 향상의 정도를 알아보고자 하였다. 차폐체 내부는 5 cm의 납이 들어 있고 작업 종사자가 앉아서 납창으로 환자를 주시하면서 주사할 수 있는 구조로 제작하였다. 새로운 차폐체 제작 전, 후 각 6개월 간 방사선 작업종사자의 분기 별 심부 피폭선량을 열형광 선량계를 이용하여 비교하고 차폐체 전면과 후면의 동일한 위치에 포켓 선량계를 위치하여 방사선 조사선량을 측정하여 비교하였다. 그리고 설문 조사를 통하여 PET/CT 작업 종사자들의 업무시 차폐체의 활용, 업무 정도, 업무 만족도 등을 조사하였다. 차폐체 제작 전의 방사선 작업 종사자의 분기 당 심부선량은 평균 2.70 mSv였으며, 방사선 차폐체 사용 후의 분기 당심부선량은 2.13 mSv로 21%의 피폭 저감효과가 나타났다. 또한 차폐체 전면의 방사선 조사선량은 분기 당 61.2 R이었고, 차폐체 후면에서는 2.8 R으로 나타났다. 설문 조사 결과종사자의 85%는 차폐체를 잘 활용한다고 하였으며, 입식보다 좌식 주사 방법에 85%의 만족도를 보였다. 차폐체의 제작, 활용 후 방사선 작업 종사자의 피폭이 감소되었으며, 이는 방사선 방호의 궁극의 목적인 방사선 피폭을 최소화 할 수 있는 병원의 근무환경과 가장 부합되는 방법이라고 생각된다. 또한 차폐체 활용이 방사선 작업 종사자의 물리적, 심리적 부담감을 경감시키고, 업무 만족도 향상에 기여한다는 것을 알 수 있었다. 이번 연구를 통해서 방사선 방호측면에서 차폐체의 제작, 활용 방안이 작업 종사자의 업무 환경에 중요한 인자임을 알려주는 좋은 결과로 사료된다. Purpose: Along with recent advances in PET/CT instrumentation and imaging technology, the number of patients has also been steadily increasing. This resulted in the increased radiation exposure to radiation workers in PET/CT rooms. In this study, we installed a radiation shield and investigated whether it could reduce radiation exposure to the workers and thus enhance job satisfaction. Materials and Methods: A radiation shield is composed of 5 cm thick lead and has a structure in which a radiation worker sits and watches a patient through lead glass while injecting radiopharmaceutical to the patient. Quarterly absorbed dose of radiation workers was measured using thermoluminescence dosimeters (TLD) and the results were compared for six months each before and after installation of the radiation shield. Exposure dose was also measured using a pocket dosimeter placed at the same location in the front and the back of the radiation shield. In addition, frequency of use of the shield and job satisfaction of radiation workers were investigated using a survey. Results: Quarterly absorbed dose of radiation workers was 2.70 mSv on average before installation of new radiation shield, whereas that dropped to 2.13 mSv after installation of radiation shield, reducing radiation exposure dose by 21%. Exposure dose on the front side of the shield was 61.2 R, whereas that on the back side of shield was 2.8 R. According to the survey, 85% of workers used the shield and were satisfied with the outcome: each radiation worker made injections to patients average of 6.5 times/day and preferred sitting to standing while injecting radiopharmaceutical to patients. Conclusion: Use of radiation shield reduced the exposure dose of radiation workers, which is the ultimate goal of radiation protection to minimize radiation exposure and is an appropriate method for the improvement of hospital working environment. Furthermore, we found that use of radiation shield not only relieves physical and psychological burden of radiation workers but also enhances job satisfaction. This result indicates that use of radiation shield is important for improvement of the radiation workers' job environment in terms of radiation protection.

PET 검사 프러시저별 방사선 차폐기구의 유용성 평가

김영선,서명덕,이완규,정요천,김상욱,서일택,송재범,Kim, Yeong-Seon,Seo, Myeong-Deok,Lee, Wan-Kyu,Jeong, Yo-Cheon,Kim, Sang-Wook,Seo, Il-Teak,Song, Jae-Beom 대한핵의학기술학회 2010 핵의학 기술 Vol.14 No.2

1994년 PET의 국내 도입 이후, 현재까지 양적으로나 질적으로 많은 발전이 있었다. 하지만 이와 함께 방사성의약품의 사용량 또한 급증하면서 검사에 있어서 가장 중요한 역할을 하는 방사선사의 개인피폭선량이 높아지는 요인으로 작용했던 것이 사실이다. 식품의약품안전청의 피폭선량관리센터에서 발표한 자료에 따르면 2008년도 방사선작업종사자의 전체 평균 피폭선량은 0.67 mSv였고, 방사선사 전체 피폭선량은 1.33 mSv로 해마다 감소하는 것으로 나타났다. 설문결과를 살펴보면 PET 검사 담당자의 평균피폭선량은 1.69 mSv였고, 1.0 mSv를 초과하는 구간에 75.3%의 방사선사가 포함되어 있었다. 이는 고 노출구간에 속한 방사선사의 비율이 높다는 것을 의미하므로, 피폭저감을 위한 노력이 요구된다. 본 연구에서는 설문조사를 통하여 PET 검사 프러시저별 차폐기구의 활용에 따른 방사선 피폭 정도를 TLD 수치를 이용하여 분석하고, 실험을 통하여 각 차폐기구의 차폐율을 측정함으로써, 그 효용성을 입증하고 적합한 차폐방법을 강구하고자 하였다. 방사선 피폭의 위험에 대해서 어느 누구보다 잘 인지하고 있는 방사선사임에도 불구하고 안이하게 생각하는 경향이 있었다. 설문결과를 살펴보면 방사선 피폭의 위험성에 대한 인식도와 피폭선량과는 크게 관련이 없었으며, 차폐기구의 활용도에 따라서는 피폭선량의 차이가 확연하게 나타났다. 프러시저 중 피폭선량에 가장 많은 영향을 미치는 단계는 방사성의약품의 투여였으며, 투여시 차폐방법에 따라 이동시 차폐방법도 달라졌다. 투여 시 차폐기구 사용현황을 보면 Both shield는 58.5%, L-Block은 20%, Syringe shield는 9%, No shield는 12.3%를 차지하였다. TLD 수치에 따른 투여 시 차폐방법은 수치가 낮을수록 Both shield와 L-block을 많이 사용하였으며, 수치가 높을수록 Syringe shield와 차폐를 시행하지 않는 경우가 많았다. 실험결과, 가장 이상적인 차폐방법은 분배 시엔 L-block을 사용하고, 이동시엔 Syringe shield carrier를 사용하며, 투여 시엔 L-block과 Syringe shield를 함께 사용하는 것이다. 환자 포지셔닝 시 Apron의 차폐율은 평균 16.4%로 차폐효과가 있다. PET 검사를 시행함에 있어서 강한 실천의지를 가지고 프러시저별로 차폐기구를 적극 활용한다면 점증하는 방사선사의 피폭 수준을 크게 감소시킬 수 있을 것으로 판단된다. Purpose: he use of PET scanners and the number of patient in Korea have been increased for recent several years dramatically. For this reason, technologists have more possibilities to be exposed to the radiation. The hospitals using PET scanners should make an effort to reduce the radiation exposure dose. The purpose of this study was to evaluate the radiation exposure does when using radiation shielding devices. The evaluation was performed through questionnaire survey and experiment. Materials and Methods: First, the technologists who had experience working in PET center in 2008-2009 were surveyed with questionnaire and TLD Figures, personal opinion of utilization of radiation shielding devices are analyzed. Second, we measured the shielding rate of shielding devices which have been using in PET study procedures. We divided the procedures into four steps; distribution, moving, injection of $^{18}F$-FDG and patient setup. Results: First, the results of this survey, using of L-block+Syringe shield, L-block, Syringe shield, No shield during the injection, were each 58.5%, 20%, 9%, 12.3%. The TLD values according to utilization of radiation shield, using both L-block+Syringe Shield and L-block showed the lower TLD values, and Syringe shield only or No shield showed the higher TLD values. Second, the results of experiments according to PET study procedures measured the shielding rates as follows. The shielding rates during the distribution using L-block, L-block+Apron shield were measured 97.4%, 97.7%. The shielding rates during the $^{18}F$-FDG delivery to the injection room using mobile Syringe shield, Syringe holder, Syringe shield carrier were each 81.7%, 98.9%, 99.7%. The shielding rates during the injection using Syringe shield, L-block, L-block+Syringe shield were measured each 51.9%, 98.3%, 98.7%. The shielding rates of Apron were measured in each 30, 60, 90, 120, 150 cm distance. The measurement were each 16.9%, 14.2%, 16.6%, 17.1%, 18.1%, 18.6%. Conclusion: The most effective method for radiation shielding is to using L-block during the $^{18}F$-FDG distribution and Syringe shield carrier during in moving $^{18}F$-FDG. For the $^{18}F$-FDG injection, L-block+Syringe shield have to be used. The shielding effect of Apron has shown average 16.4%. According to the survey of questionnaire, the operators recognized well risk of the radiation exposure but, tended ignore in working. The radiation dose according to recognition of radiation exposure risk was not relevant. but radiation dose according to utilization of radiation shield lower the more use it. The main reason of no use of shielding devices is cumbersome, 55% of the respondents answered. I'm sure, by use of radiation shield in all PET procedure, radiation exposure will be reduced considerably.

Y-90 microsphere 로부터 생성되는 제동복사선의 차폐를 위한 차폐체 개발 연구

박준영,Park, Jun Young 대한핵의학기술학회 2019 핵의학 기술 Vol.23 No.1

본 연구는 고에너지의 베타선을 방출하는 Y-90 미세구의 경동맥방사선색전술 시 발생되는 제동복사선에 의한 불필요한 외부피폭을 줄이고자 텅스텐 차폐체를 개발하였다. 본 연구에서는 다양한 용량(1 GBq, 2 GBq, 4 GBq)의 $SIR-Spheres^{(R)}$ Y-90 미세구를 사용하여, 텅스텐 차폐체 표면으로부터 10 cm, 50 cm, 100 cm인 곳에서 GM tube식 디지털 서베이미터로 선량률을 측정하였다. 텅스텐 차폐체 표면 10 cm 위치에서 차폐율을 분석한 결과 4 GBq의 $SIR-Spheres^{(R)}$ Y-90 미세구의 경우 90.9%, 2 GBq의 경우 88.9%, 1 GBq의 경우 88.8%의 차폐율을 보였고, 표면 50 cm 위치에서 차폐율은 4 GBq의 $SIR-Spheres^{(R)}$ Y-90 미세구의 경우 89.2%, 2 GBq의 경우 87.5%, 1GBq의 경우 86.3%로 나타났다. 텅스텐 차폐체 표면 100 cm 위치에서 텅스텐 차폐체는 평균 75.1%의 차폐율을 보이는 것으로 확인할 수 있었다. 높은 용량이 함유된 $SIR-Spheres^{(R)}$ Y-90 미세구의 경동맥방사선색전술시 방사선 작업종사자와 선원간의 거리가 짧고, 작업시간이 길기 때문에 제동복사선에 의한 피폭에 노출될 수 있다. 본 연구를 통해 개발된 텅스텐 차폐체는 향후 임상에서 경동맥방사선색전술 시 제동복사선에 의한 외부피폭을 줄이는데 활용될 수 있을 것이라 기대 된다. Purpose Yttrium-90 (Y-90) is high-energy beta emitters ($E{\beta}$, max = 2.28 MeV) with the mean penetration depth of 2.5 mm in tissue. Radioactive microspheres containing Y-90 is widely used for the transarterial radioembolization of hepatocellular carcinoma. However, bremsstrahlung radiation from Y-90 can cause the external radiation exposure to medical staff who handle the Y-90 microspheres. In this study, shielding device for Y-90 microspheres was developed to minimize the external radiation exposure. Materials and Methods Y-90 microsphere shielding device was made from 6 mm thicknesses of tungsten including the lead glass window. Radiation shielding ability of Y-90 microsphere shielding device was evaluated using 4 GBq of $SIR-Spheres^{(R)}$ Y-90 microspheres. The bremsstrahlung radiation was measured using radiation survey meter. Results The mean radiation dose of Y-90 microspheres in acrylic shield was $261.7{\pm}2.3{\mu}Sv/h$ (n=5) at 10 cm away from the shield. With the additional tungsten shielding device, it was $23.7{\pm}1.3{\mu}Sv/h$ (n=5). Thus, the bremsstrahlung radiation dose was decreased by 90.9%. At 50 cm away from the shield, bremsstrahlung radiation was reduced by 89.2% after using tungsten shielding device. Conclusion During the preparation and radioembolization of Y-90 microsphere, medical staff are exposed to external radiation. In this study, we demonstrated that the use of tungsten shielding device devices significantly reduced the amount of bremsstrahlung radiation. Y-90 microsphere tungsten shielding device can be highly effective in reducing the bremsstrahlung radiation.

A New Radiation-Shielding Device for Restraining Veterinary Patients

Songyi Kim,Minju Lee,Miju Oh,Yooyoung Lee,Jiyoung Ban,Jiwoon Park,Sojin Kim,Uhjin Kim,Jaepung Han,Dongwoo Chang The Korean Society of Veterinary Clinics 2023 한국임상수의학회지 Vol.40 No.6

In veterinary medicine, most radiographic images are obtained by restraining patients, inevitably exposing the restrainer to secondary scattered radiation. Radiation exposure can result in stochastic reactions such as cancer and genetic effects, as well as deterministic reactions such as skin burns, cataracts, and bone marrow suppression. Radiation-shielding equipment, including aprons, thyroid shields, eyewear, and gloves, can reduce radiation exposure. However, the risk of radiation exposure to the upper arms, face, and back remains, and lead aprons and thyroid shields are heavy, restricting movement. We designed a new radiation-shielding system and compared its shielding ability with those of conventional radiation-shielding systems. We hypothesized that the new shielding system would have a wider radiation-shielding range and similar shielding ability. The radiation exposure dose differed significantly between the conventional and new shielding systems in the forehead, chin, and bilateral upper arm areas (p < 0.001). When both systems were used together, the radiation-shielding ability was better than when only one system was used at all anatomical locations (p < 0.01). This study suggests that the new radiation-shielding system is essential and convenient for veterinary radiation workers because it is a step closer to radiation safety in veterinary radiography.

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

김상태 한국콘텐츠학회 2018 International Journal of Contents Vol.14 No.4

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.

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

Kim, Sang-Tae The Korea Contents Association 2018 International Journal of Contents Vol.14 No.4

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.

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

Sang-Tae Kim 한국콘텐츠학회(IJOC) 2018 International Journal of Contents Vol.14 No.4

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.