• Journal of the Korean Society of Radiology
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• v.16 no.4
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• pp.373-379
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• 2022

The radiation source used for non-destructive testing have permeability and cause a scattered radiation through collisions of surrounding materials, which causes changes in the surrounding spatial dose. Therefore, this study attempted to evaluate and analyze the distribution of spatial dose by source in the working environment during the non-destructive test using monte carlo simulation. In this study, Using FLUKA, a simulation code, simulates ⁶⁰Co, ¹⁹²Ir, and ⁷⁵Se source used in non-destructive testing, The reliability of the source term was secured by comparing the calculated dose rate with the data of the Health and Physics Association. After that, a non-destructive test in the radiation safety facility(RT-room) was designed to evaluate the spatial dose according to the distance from the source. As a result of the spatial dose evaluation, ⁷⁵Se source showed the lowest dose distribution in the frontal position and ⁶⁰Co source showed a dose rate of about 15 times higher than that of ⁷⁵Se and about 2 times higher than that of ¹⁹²Ir. In addition, the spatial dose according to the distance tends to decrease according to the distance inverse square law as the distance from the source increases. Exceptionally, ⁶⁰Co, ¹⁹²Ir, and ⁷⁵Se sources confirmed a slight increase within 2 m of position. Based on the results of this study, it is believed that it will be used as supplementary data for safety management of workers in radiation safety facilities during non-destructive testing using radioactive isotopes.

• Journal of Radiation Protection and Research
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• v.15 no.1
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• pp.9-13
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• 1990

1959년 한국원자력연구소가 창립됨과 동시에 &Health Physics&, 즉 보건물리라고 하는 명칭과 조직이 탄생되어, 방사선안전관리의 실무와 보건물리의 연구가 시작되었다. 최초 10년간은 선진제국의 보건물리분야의 연구와 기술을 추적하여 우리나라의 방사선안전관리 기술의 기초를 다지는 시기로서 개인방사선모니터링기술, 환경방사선(능) 모니터링기술 및 방사선방어용계측기기의 교정기술 개발에 중점을 두고 연구개발이 추진되었으며, TRIGA Mark-II 연구용원자로의 가동에 따라 원자로 생체차폐체의 건전성 검증에 관한 유익한 방사선량 측정자료도 얻게 되었다. 즉 이 기간은 방사선안전관리의 체제정비 및 기초기술 확립에 노력한 기간이었다. 1970년대는 원자력 연구개발에 대한 기본방향과 정책의 변경등으로 보건물리 연구조직은 방사선안전관리, 환경연구 그리고 방사화학분야로 분산되었으며, 그로인하여 연구개발활동은 거의 정체되어 겨우 방사선안전관리 실무만이 그 명맥을 유지하였다. 그 결과 우리나라 방사선안전관리 및 그와 관련된 연구개발의 기반이 흔들리게 되었으나, 그러한 환경하에서도 방사선량측정평가기술, 방사선차폐설계기술 및 원자로사고시 피폭선량평가기술의 선진화에 필요한 지식을 얻었으며, 방사선 안전관리에 유익한 실무경험도 축적하게 되었다. 1980년대는 통합된 원자력 연구개발체제의 구축으로 방사선작업종사자 및 일반공중의 피폭저감화 기술개발에 필요한 각종 최신기술을 도입하였고, 관리업무에 있어서도 측정의 정확도와 신뢰성향상 및 새로운 관리기술의 개발에 많은 노력을 한 결과, 유익한성과를 얻게된 기간이다. 특히, 이 기간은 방사선안전관리기술의 선진화를 위한 지식이 축적되어 90년대의 방사선안전관리기술자립화를 위한 전환기로서, 이와같이 축적된 기술은 원자력의 평화적 이용에 크게 기여할 것으로 기대된다.서 dithiothreitol를 투여한 군에서는 우라늄단독투여군에 비해 cretinine의 배설이 상당히 증가하였다(P<0.05). 6. 우라늄오염에 의한 신장의 소견에 있어 우라늄단독투여군은 근위곡세뇨관상피의 공포화 및 종창, microvilli와 brush border의 손실, 세뇨관 상피의 괴사가 관찰되었으며, 간장의 충혈, 중심성 괴사 및 모세관 확장증도 관찰되었다. 그리고 sodium bicarbonate와 생리적 식염수를 병행투여한 군과 우라늄을 투여하고 30분이 지나서 dithiothreitol를 투여한 군에서는 우라늄 단독투여군에 비해 높은 방호효과가 관찰되었으나 다른 실험군에서는 큰 효과가 없는 것으로 나타났다. 결론적으로 우라늄의 체내오염시에는 sodium bicarbonate와 생리적 식염수를 가능한 빨리 병행투여하거나 dithiothreitol을 체내오염후 30분이 지나서 투여하는 방법이 우라늄오염에 대한 제염에 매우 유효할 것으로 생각되며, 특히 우라늄에 의한 인체장해를 유의하게 경감시켜줄 것으로 사료되었다.내의 어떤 부위와도 관계가 되는 것으로 간주되는데 이것이 $(^3H)$ QNB가 $(^3H)$ NMS보다 높은 최대 결합능력 $(B_{max})$을 나타낼 이유이다. (b) 두 종류의 다른 제제에서 우리는 같은 양상의 결과를 관찰하었기에 결점이 많은 homogenates 제제보다는 intact cell aggregates 제제를 수용체 연구에 대한 새로운 실험모형(experiment model)으로 사용할 수 있는 가능성을 제시하고자 한다.$가 38.8%로 가장 많고, 그 다음이 ${\ulcorner}$l9세(歲)이후${\lrcorner}$가 25.2%로서 전체

• Journal of the Korean Society of Radiology
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• v.5 no.3
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• pp.135-141
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• 2011

If protective performance of apron cannot be good, radiation exposure of an guardian or a patient, a person engaged in radiation related industry cannot rise. Therefore, It will be evaluated protection performance to radiation protection aprons by manufacturers and lead equivalent more than 0.25mm lead equivalent. And, will show in the direction of application to clinic. The new aprons by manufacturers(H, X, I, J company) and lead equivalent(0.50mmPb, 0.35mmPb, 0.25mmPb) measured transmitted dose rate and shielding rate, uniformity under fluoroscopy and general radiography using to fluoroscopy system and digital radiography system, x-ray multifunction meter. The shielding rate measurement results, 0.5mmPb apron was Shielding rate of apron of a I company(fluoroscopy : 97.96%) was the best under six companies, and shielding rate of apron of a J company(fluoroscopy : 96.25%) was worst. 0.35mmPb Apron was Shielding rate of a I company(fluoroscopy : 96.79%) was the best under the three companies, and shielding rate of an H company(fluoroscopy : 95.81%) was the worst. 0.25mmPb Apron was Shielding rate of X company apron(fluoroscopy : 90.908%) was better than H company apron(fluoroscopy : 88.82%) than two companies. The uniformity measurement results, 0.5mmPb Aprons of X company(fluoroscopy : 0.13) and I company(fluoroscopy : 0.19) was the best under the six companies, and J company apron(fluoroscopy : 0.45) was the worst. 0.35mmPb. Along a manufacturer and lead equivalent performance of apron protection is distinguished certainly. Therefore, a patient, guardian or a person engaged in radiation related industry shall enforce experiment of a lot of ways defined or evaluation so that the maximum reduces radiation exposure. Buy the apron that protective performance is good, It will be performed through experiment and evaluation.

• Journal of the Korean Society of Radiology
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• v.16 no.4
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• pp.381-386
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• 2022

Non-Destruction Test (NDT) is a method to check internal defects without destroying the product. Among them, radiographic testing (RT) uses high-energy radiation, so it is very important to prevent radiation exposure of workers. Therefore, in this study, in this study, a radiation sensor structure that improves radiation detection performance compared to the existing PbI₂ and can immediately detect accidents in RT was presented. For evaluation, the conversion efficiency was analyzed in the gamma ray source through FLUKA simulation. PbI₂ with overlapping Gd₂O₂S:Tb presented in this study showed a higher radiation sensitivity from 1.22 to 3.22 times than that of non-overlapping PbI₂. This indicates that the presented sensor is suitable for use as a radiation sensor for source detection in RT.

• Journal of radiological science and technology
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• v.28 no.2
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• pp.117-122
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• 2005

According to the Para. 5 of Art 2 of the Korean Nuclear Safety Regulations, which was revised in 1999, internal dose assessment as well as external one should be performed by law for employees at a nuclear power plant from 2003, and their estimate errors should also be within 50%. Thus, more accurate internal dosimetry becomes important. Corresponding to such regulation revision, we are developing a more accurate thyroid-uptake internal dosimetric system and have developed a Monte Carlo simulation code, the so-called CALEFF, to calculate the detection efficiency of the dosimetric system. In this paper, we calculated detection efficiencies with various test conditions by using the CALEFF code and discussed their characteristics. We may use the detection efficiency calculated by the code in calibrating the thyroid internal dose from measured data.

• Journal of the Korean Society of Radiology
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• v.5 no.5
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• pp.237-244
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• 2011

Generally, X-ray examinations for dentistry use low energy radiation. It explains that the radiations are mainly absorbed to a human body because of the weak permeability. We made up some counterplans for decrease in radiation exposure, when guardians and radiologists are overexposed owing to unavoidable circumstances. The equipments for the test are GX-770 and CRANEX TOME CEPH which are used for various exams. Besides we measured the radiations in the projection room and in the control room using model 2026c and 20X6-1800. According to the test, the measurement value in the control room was low dose below $20{\mu}R$, the maximum dose in the projection room was $702.8{\mu}R$ and the measurement value of back dose was higher than lateral one. As the result, if we use a shielding door, it's effective for radioprotection and when we didn't prepare protectors, we should secure appropriate distance and be situated at the side area($90{\sim}135^{\circ}$) on the basis of centeral radiation. That way will provide valuable aid for radioprotection.

• Journal of Radiation Protection and Research
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• v.24 no.4
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• pp.215-223
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• 1999

Characteristics of radiation field in the steam generator(S/G) water chamber of a PWR were investigated and the anticipated effective dose rates to the worker in the S/G chamber were evaluated by Monte Carlo simulation. The results of crud analysis in the S/G of the Kori nuclear power plant unit 1 were adopted for the source term. The MCNP4A code was used with the MIRD type anthropomorphic sex-specific mathematical phantoms for the calculation of effective doses. The radiation field intensity is dominated by downward rays, from the U-tube region, having approximate cosine distribution with respect to the polar angle. The effective dose rates to adults of nominal body size and of small body size(The phantom for a 15 year-old person was applied for this purpose) appeared to be 36.22 and 37.06 $mSvh^{-1}$) respectively, which implies that the body size effect is negligible. Meanwhile, the equivalent dose rates at three representative positions corresponding to head, chest and lower abdomen of the phantom, calculated using the estimated exposure rates, the energy spectrum and the conversion coefficients given in ICRU47, were 118, 71 and 57 $mSvh^{-1}$, respectively. This implies that the deep dose equivalent or the effective dose obtained from the personal dosimeter reading would be the over-estimate the effective dose by about two times. This justifies, with possible under- or over- response of the dosimeters to radiation of slant incidence, necessity of very careful planning and interpretation for the dosimetry of workers exposed to a non-regular radiation field of high intensity.

• Journal of Digital Contents Society
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• v.13 no.3
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• pp.421-429
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• 2012

Lately, the number of interventional radiology is increased by the extension of procedure in medical radiation, and radiation exposure may be appeared differently by interventional radiologists, it is caused increase of radiation dose for radiation worker, patient, and radiologists. This study has done a comparative analysis characteristic of radiation exposure for five radiologists who executed interventional cardiology for 303 patients in S university hospital of Gyeong-Buk from Nov. 1, 2011 to Jan. 31, 2011. The average exposure time of five radiologists was 697.95sec. The average of cumulative DAP(exp) for patients was $52,730mGycm^2$ and the average of total DAP for patients was $104,875.14mGycm^2$. The average of frames for image was 855.52 frames in acquired images, and the average of frames for images was 802.2 frames in exposure images. They were statistically significant differences (p<0.05). Exposure time, cumulative DAP(fluro), cumulative DAP(exp), total DAP, acquired image, and exposure image were high correlation except cumulative DAP(exp), and acquired runs in x-ray exposure characteristics of machine. Exposure time was a great influence on radiologist. It signified that the more exposure time lead to the more radiation dose for radiologist. Radiation dose is related to ability, experience, difficulty, and precision of procedures in interventional procedure. The number of angiography and exposure time is difficult to control by radiologists. Therefore, it is in need of reasonable system which was evaluated the real dose of medical teams in interventional proceedings. We think that self education and training are required to reduce radiation dose for radiologists and radiation workers.

• Journal of Radiation Protection and Research
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• v.20 no.3
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• pp.163-168
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• 1995

The Radio-frequency electromagnetic(RFEM) spectrum is defined as waves that range in frequency from>0 to $3{\times}1012Hz$. Although there are several thousands of reports that present data or opinion of the biological response to RFEM radiation, no consensus has emerged regarding thresholds and mechanisms of injury. This review presents a overview of the subject on mechanisms of interaction of RFEM fields with tissue, chromosomal and mutagenic effect. carcinogenic effects. The scope of the review is expanded to include systemic effects such as those on reproduction, growth, and development, hematological effects. Some biological end points, those with associated with behavior and cataractogenesis is discussed.

• Journal of Radiation Industry
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• v.11 no.1
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• pp.47-54
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• 2017

Compared to other occupations, there is a greater risk of exposure to radiation due to the use of radioisotopes in nuclear medicine for diagnostic evaluations and therapy. To consider ways to reduce exposure dose for those in nuclear medicine involved in injection work and elution work among radiation workers as well as for sanitation workers and trainees among frequent workers an investigation into exposure dose and situational analysis from changes in yearly exposure dose evaluations, changes in work environment and changes in forms of inspection were conducted. Exposure dose measurements were taken by using EPD MK2 worn during working hours for one injection worker, one elution worker, two sanitation workers, and one trainee at a general hospital in the Seoul area for three days from July 18th to 20th 2016. Radiation from radioisotopes which are a part of nuclear medicine can significantly affect not only radiation workers who deal with radioisotopes directly but also frequency works as well. According to this study the annual dose limit for elution workers and injection workers were considered safe as the amount of exposure was not large enough to have a significant effect. The limits of this study consist in the duration of this study and the quantity of participants. Also there was a limitation of the measurement device involving accumulated exposure, where the EPD MK2 cannot check the changes in exposure according to a particular activity.