Beam hardening artifact can be caused by metal material when performing PET exam. Therefore, we studied a solution decreasing artifact caused by metallic dental implant. The higher voltage, the lesser artifact in CT exam. But Higher voltage dosen't affect PET exam. The thicker silicon the lesser artifact in CT and PET exam. Both methods make less artifact in CT and PET exam. But considering safety of patient, the way of using silicon is better.

This study was to improve to utilization of non dosimetry measurements for X-ray radiography. Experiments was passed off varying the X-ray tube voltage and the thickness of the aluminum filter by actual dose. Calculated results was set to the first beam quality factors, calculated first correction coefficient by the Microsoft Excel program was set as the second beam quality factors. To make the non dosimetry measurements simply, the Excel program apply to the new beam quality factors, the error was compared to the previous studies, and the results verify the calculated value of smaller errors.

The purpose of this study was to investigate radiation dose sensitivity due to displacement of human extremities in the water bolus box on radiation therapy. Water bolus box and human thigh with femur bone were constructed in computerized radiation therapy planning system to verify the absorbed dose. Two 6MV X-ray beams were irradiated bilaterally into water bolus box and then radiation dose were calculated each situation at displacement of middle axis of thigh from the center in water bolus box to right and left direction. Absorbed dose of thigh and femur bone increased by the distance of displacement. The maximum dose of thigh even increased 20% over than prescribed dose. This is in contrast to conventional concept of dose distribution in water bolus box. Based on this result, displacement of body site in the water bolus box have to be averted during radiation therapy.

This study analyzed the total number of 19,636 patients and radiation technologists, 11,433 of male and 8,203 of female by examined body parts, age, types of detectors, the using contrast enhancement and working condition of the technologists, regular staffs or rotation-duty staffs, based on the K-DOS program distributed by FDA with the DLP value of diagnostic evaluation. The result shows that the effective radiation dose was 0.7mSv~41.7mSv for each region and male patients had more radiation exposure than females. And the amount of exposure was also affected by the types and the method of detectors. Furthermore, the regular staffs took the role of helping the patient to get reduced amount of radiation exposure than rotation duty-staffs. Computed tomography (CT) use has increased dramatically over the past several decades. In this reason, to support the patients and the workers’ health in the field, the hospitals should apply specialized regular working radiation technologist system and manufacturing companies of those CTs should develop low medical radiation exposure devices.

4종 해충(복숭아혹진딧물, 점박이응애, 아메리카잎굴파리, 대만총채벌레)에 이온화에너지인 전자빔과 X-ray를 각각 조사하여 이들 해충 의 발육과 생식에 미치는 영향을 비교하여 억제선량을 결정하였다. 복숭아혹진딧물 약충에 전자빔과 X-ray 조사 시, 전자빔의 경우에는 100 Gy, X-ray의 경우에는 30 Gy에서 우화성충의 산자가 완전히 억제되었다. 복숭아혹진딧물 성충의 경우 200 Gy (전자빔)와 50 Gy (X-ray)에서 각각 F1 세대 약충의 우화가 억제되었다. 그러나 이들 두 이온화에너지 모두 성충수명에는 영향을 주지 않았다. 점박이응애의 알에서는 전자빔 150 Gy와 X-ray 50 Gy 선량에서 알의 부화가 완전히 억제되었다. 아메리카잎굴파리 번데기에서는 X-ray 조사선량이 증가할수록 우화율이 감소하 였다. 대만총채벌레 성충에 조사 시 전자빔의 250 Gy와 X-ray의 200 Gy 선량에서 F1 세대 알의 부화가 완전히 억제되었다.

The purpose of this study was to minimize of entrance surface dose (ESD) at the eye using high kVp technique in the computed radiography. We used REX-650R (Listem, Korea) general X-ray unit, and external detector with ESD dosimeter of Piranha 657 (RTI Electronics, Sweden). We used head of the whole body phantom. The total 64 images of X-ray anterior-posterior of skull were acquired using the film/screen (F/S) method and the digital of computed radiography method. The three radiology professor of more 10 years of clinical career evaluated a X-rays images in the same space by 5-point scale. The external detector was performed measurement of ESD of three times by same condition on the eye of the head phantom. The good image quality in the F/S method (90 kVp, 2.5 mAs) showed at the minimized ESD of 0.310 ± 0.001 mGy. the good image quality in the computed radiography method (90 kVp, 2.0 mAs) showed at the minimized ESD of 0.180 ± 0.002 mGy (P = 0.002). Finally the radiation dose could reduced about 50% in the computed radiography method more than the F/S method. In addition the eye entrance surface dose using high kVp technique with the computed radiography was reduced 92% more than conventional technique (F/S method).

This research was conducted to know application of Photostimulated luminescence (PSL) and Thermoluminescence (TL) methods by irradiation dose for leaching tea, sauces and starch approved in Korea. Leaching tea, sauces and starch powder were treated with 60Co gamma ray at dose 0~10 kGy for detection trial whether they are irradiated or not by measuring PSL and TL for whole samples. PSL values were less than threshold value 700 and were negative for non-irradiated samples but more than 5,000 and were positive for irradiated ones. PSL results of leaching tea and sauces showed the correct identification for non-irradiated and irradiated samples, respectively except starch samples. To enhance the reliability of the TL result, the first glow curve (TL1) was compared with the second glove curve (TL2) obtained after a re-irradiation step at 1 kGy. The TL ratio (TL₁/TL₂) was in good agreement with the reported TL threshold for both the non-irradiated (< 0.1) and irradiated (> 0.1) samples. TL results of leaching tea, sauces, starch showed the correct identification for non-irradiated and irradiated samples, respectively. This study was performed to know application of PSL and TL methods for leaching tea, sauces and starch, and the methods were able to detect the irradiation products.

The importance of managing the exposure to radiation for radiological technologist is becoming more conspicuous as modern medical care increases the number of hospital exams involving radiation and as work of radiological technologists expand and increase in areas using advanced medical equipment for diagnosis and treatment purposes involving radiation. Measurements for individual exposure dose to radiation can differ according to the equipment and facilities in the work environment and the average number of exposures an individual is involved in. Therefore, systematic and reasonable controls on the exposure dose to radiation can be attained from core data. Shallow dose/Deep dose measurements were taken according to the year of the measurement, the technologist’s occupation post, gender, department, and age over a five year period from January 1, 2003 to December 31, 2007 using a sample of radiological technologists from ten general hospitals throughout S. Korea. When comparing individual exposure dose of each radiological technologist, there was no significant difference in the mean exposure dose according to the year the measurement was taken (p>0.05). Mean exposure dose for Deep/Shallow according to gender showed that men received significantly higher exposure dose than women (p<0.001). Mean exposure dose for Deep/Shallow according to age showed an increase in exposure dose as age decreases, however, it was not statistically significant (p>0.05). According to occupation post, technologists working in nuclear medicine received significantly higher dose than other occupation posts (p<0.001). The results of individual exposure dose were under the dose limits in accordance to all nuclear regulations. Furthermore, since stochastic effects may occur with long-term exposure to low level radiation, individual exposure dose data was thoroughly managed and the principle of As Low as Reasonably Achievable (ALARA) was implemented when establishing the design of this study.

The changes in DNA damage were investigated during storage after irradiation. Potato, garlic were irradiated at 0.05, 0.07, 0.1 and 0.15 kGy and stored for 3 months. Ginger was irradiated at 0.01, 0.02, 0.03, 0.04 and 0.05 kGy and stored for 1 month. The comet assay was applied to the sample immediately after irradiation and at the end of storage. Samples were isolated, grounded and the suspended cells were embedded in an agarose layer. After lysis of the cells, they were electrophoresed for 1 min. and then stained. DNA fragmentation in seeds caused by irradiation was quantified as tail length and tail moment (tail length ×% DNA in tail) by comet image analyzing system. Right after irradiation, the differences in tail length between unirradiated and irradiated samples were significant(p〈0.05) in potato, garlic and ginger. With increasing the irradiation doses, statistically significant longer extension of the DNA from the nucleus toward anode was observed. The results represented as tail moment showed similar tendency to those of tail length. Similarly in the stored samples, even 1 or 3 months after irradiation, all the irradiated samples significantly showed longer tail length than the unirradiated controls. These results indicate that the comet assay could be one of the simple methods of detecting irradiated samples. Moreover, the method could detect DNA damage even after 1 or 3 months after irradiation.

The changes in DNA damage were investigated during storage after irradiation. Beef, pork and chicken were irradiated at 1.0, 3.0 and 5.0 kGy and stored for 6 months at -20℃. The comet assay was applied to the sample muscles at the beginning of irradiation and at the end of storage. Muscles were isolated, sliced, and the suspended cells were embedded in an agarose layer. After lysis of the cells, they were electrophoresed for 2 min. and then stained. DNA fragmentation in tissues caused by irradiation was quantified as tail length and tail moment (tail length × % DNA in tail) by comet image analyzing system. Right after irradiation, the differences in tail length between unirradiated and irradiated muscles were significant(p〈0.05) in beef, pork and chicken. With increasing the increasing doses, statistically significant longer extension of the DNA from the nucleus toward anode was observed. Similarly even 6 months after irradiation, all the irradiated muscles significantly showed longer tail length than the unirradiated controls. The results represented as tail moment showed similar tendency to those of tail length, but the latter parameter was more sensitive than the former. These results indicate that the comet assay could be one of the simple methods of detecting irradiated muscles. Moreover, this method suggest that using comet assay, we were able to detect DNA damage differences even after 6 months after irradiation.

LiF(Mg,Cu,Na,Si) 형광체의 γ선과 β선에 대한 TSEE 특성을 조사하였다. 상(60)Co γ선에 대한 감도는 약 450 counts/mR이었고, 여러 가지 β선에 대한 TSEE 에너지 의존성은 β입자의 평균에너지 0.02MeV에서 0.8MeV 사이에서 ±10%이었다. 그리고 제작된 형광체 앞면에 7mg.cm 상(-2)의 인체 등가물질을 두 면 입사 β입자의 에너지에 무관하게 피부 흡수 선량을 측정할 수 있었다.

한국원자력환경공단은 처분시설 내 1단계 인수·저장구역의 인수검사 공간 및 드럼 취급 공간 부족에 대한 문제를 해결하기 위하여 방폐물검사건물을 건설하여 저장·처리능력을 확충할 예정이다. 본 연구에서는 MCNP 코드를 이용하여 방폐물검사 건물 내 저장구역에서 취급하는 해체 방사성폐기물 대상 신형처분용기를 대상으로 작업종사자의 피폭선량을 평가하였다. 평가결과, 시설 내 저장 가능한 최대 용기 개수(304개)와 방사선작업에 대한 연간 예상 작업시간(약 306시간)에 대하여 연간 집단선량은 총 84.8 man-mSv로 계산되었다. 시설 내 총 304개의 신형처분용기(소형/중형 타입)가 저장 완료된 시점에서 인수검사, 처분검사를 위한 작업종사자의 투입인력은 총 25명, 작업종사자 당 예상피폭선량은 연평균 3.39 mSv로 산출 되었다. 소형용기 취급 시 작업종사자의 고방사선량 작업에 따른 작업효율과 방사선적 안전성 확보를 위해서는 콘크리트 라이너의 두께를 증가시키는 추가적인 차폐가 필요할 것으로 평가되었다. 향후 본 연구를 바탕으로 실측기반의 해체폐기 물의 선원항과 특성을 활용하여 방사선작업 당 작업시간 및 투입인력을 산출함으로써 작업종사자의 최적의 방사선작업조건을 도출할 수 있을 것으로 사료된다.

원전 해체 공정 중 다량의 콘크리트 방사성 폐기물의 절단 과정에서 불가피하게 방사성 에어로졸이 생성된다. 방사성 에어 로졸은 인체 호흡기 흡착에 의한 내부피폭을 유발하기 때문에 작업자의 방사선 방호를 위한 내부피폭평가가 필수적으로 시행되어야 한다. 그러나 실제 작업환경의 에어로졸 특성값을 사용하기에는 선행 연구가 미비하며 콘크리트에 포함된 방사성 핵종의 수가 많기 때문에 정확한 작업자 내부피폭평가를 위해서는 상당한 시간과 인력이 필요하다. 따라서, 본 연구에서는 사전 연구된 콘크리트 에어로졸 특성값을 활용하여 원전 해체 전 절단 작업자의 내부 피폭량을 빠르게 예측할 수 있는 새로운 방법론을 제시하고자 한다. 본 연구팀은 콘크리트 절단 시 발생하는 사전 연구에서 발표된 에어로졸의 수농도 크기 분포데이터를 뉴턴-랩슨법을 이용하여 피폭평가 계산에 필요한 방사능중앙 공기중역학직경(Activity Median Aerodynamic Diameter)값으로 변환하였다. 또한 원전 정지 10년 후 비방사능 값을 ORIGEN code로 계산하였으며, 최종적으로 핵종별 예 탁유효선량을 IMBA 프로그램을 이용하여 계산하였다. 핵종별 예탁유효선량값을 비교한 결과 152Eu에 의한 최대 예탁유효선량은 전체 선량값의 83.09%를 차지하고, 152Eu를 포함한 상위 5개 원소(152Eu, 154Eu, 60Co, 239Pu, 55Fe)의 경우 최대 99.63%를 차지함을 확인하였다. 따라서 원전 해체 전 콘크리트의 구성 원소 중 상위 5개 주요 원소 측정을 먼저 시행한다면 더 빠르고 원활한 방사능 피폭관리 및 해체 작업 안전성 평가가 가능할 것으로 판단된다.

일반촬영의 저관전압 촬영에서 발생되는 저 에너지 X-선은 신체에 흡수가 많고 영상 품질 향상에는 도 움을 주지 못한다. 본 연구에서는 일반 촬영에서 적정 농도를 유지하면서 환자의 피폭 선량을 줄이기 위해 농도에 따른 관전압 15%법칙과 농도에 비례하는 관전류량을 이용하여 면적 선량과 입사표면선량을 측정 하여 환자의 피폭선량을 비교하였다. Hand, Knee, Abdomen, Skull 촬영에서 kVp를 115%까지 증가하면서 mAs를 50%까지 감소시키고, kVp를 85%까지 감소시키고 mAs를 200%까지 증가시키면서 면적선량과 입사표 면선량을 측정하여 각각의 선량을 비교하였다. 그리고 각 영상의 5군데를 정하여 농도를 측정하고 Kruskal wallis H 검증을 하여 집단–간의 유의확률을 알아보았다. 농도를 일정하게하기 위해 관전압을 115%로 증가 하고, 관전류를 50%로 감소시킨 조건에서 각 부위별 평균 면적선량과 입사표면선량을 측정한 결과 기준 선량을 100%로 할 때 각각 58.68%, 59.85%로 감소하고, 관전압을 85%로 감소하고 관전류를 200%로 증가시킨 조건에서 각각 147.28%, 159.9%로 증가하였다. 농도 변화를 비교한 결과 Hand, Knee, Abdomen, Skull 촬영 모두 유의확률 >0.05 나타나 농도 변화는 없는 것으로 나타났다. 해상력과 대조도에 영향을 주지 않는 범위에서 적정한 계산을 통해 관전압을 증가시키고 관전류를 낮게 해서 촬영하는 것이 적정농도를 유지하면서 환자의 피폭 선량을 줄이는 간단한 방법으로 사료된다.