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.

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.

The purpose of the study was to evaluation of the radiation dose reduction using various automatic exposure control (AEC) systems in different manufactures multi-detector computed tomography (MDCT). We used three different manufacturers for the study: General Electric Healthcare, Philips Medical systems and Siemens Medical Solutions. The general scanning protocol was created for the each examination with the same scanning parameters as many as possible. In the various AEC systems, the evaluation of reduced-dose was evaluated by comparing to fixed mAs with using body phantom. Finally, when we applied to AEC for three manufacturers, the radiation dose reduction decreased each 35.3% in the GE, 58.2% in the Philips, and 48.6% in the Siemens. This applies to variety of the AEC systems which will be very useful to reduce the dose and to maintain the high quality.

The National Health Insurance Act, the Industrial Health Act and the School Health Act require chest radiography at least once a year. In chest radiographic examination, most group examinations use indirect X-ray primarily aiming at diagnosing diseases and enhancing people's health. This study purposed to minimize radiation exposure dose by comparing it between direct and indirect chest X-ray studies. According to the result of comparing and analyzing radiation exposure dose, the average incident dose and penetrating dose were 0.929μGy and 0.179μGy respectively in direct chest X-ray and 6.807μGy and 1.337μGy in indirect chest X-ray In order to minimize radiation exposure dose at direct and indirect chest X-ray, indirect X-ray should be excluded from group examination if possible. Moreover, it is necessary to control the quality of equipment (Q/A & Q/C) systematically and to avoid using unqualified equipment in order to reduce radiation exposure dose.

저선량 γ선 조사가 참박의 초기생육과 생리활성에 미치는 효과를 알아보기 위하여 참박 종자에 γ선을 0-2O Gy 수준으로 조사하여 생육을 관찰하였다. 저선량 γ선에 의한 참박의 초기생육은 대조구에 비해 4-16Gy에서 다소 증가하였고, 생육 조사시 측정한 자엽의 경우 catalase와 Peroxidase 활성이 대조구에 비해 8 Gy 조사구에서 가장 높았으며 본엽은 peroxidase활성이 4 Gy 조사구에서 확연히 증가

저선량 γ선 조사가 기내 유기한 대지와 수미 감자 소괴경의 맹아율과 식물체 생장 및 생리활성에 미치는 효과 등을 알아보고자 감자 소괴경의 저장기간별로 γ선을 0.5~30Gy 까지 조사하여 pot실험을 수행하였다. 감자 소괴경의 휴면과 생육에 대한 저선량 γ선 효과는 품종과 저장기간에 따라 다소 차이가 있었다. 대지 품종의 경우 대체로 2,4,8Gy에서 대조구에 비해 높은 맹아 출현율을 보였고,

저선량 방사선 조사한 고추 2품종, 조광고추와 조흥고추의 종자 발아율과 초기생육 및 고추 유식물체의 후속 고선량에 대한 내성 변화를 알아보고자 저선량 0, 4, 8, 20, 50 Gy를 조사하여 재배한 고추 유식물체에 γ선 50 Gy와 100 Gy를 조사한 후 생육상황을 관찰하였다. 저선량 조사한 고추 유식물체의 초기생육 촉진과 후속고선량 내성은 품종에 따라 달랐는데, 조광고추보다 조홍고추 품종에서 뚜렷한 증가효과를 나타냈고 발아율과 초

저선량 γ선이 시판중인 배추 신규종자인 "만점" 배추와 묵은 종자인 "서림엇갈이" 배추의 발아와 초기생육 및 생리활성에 미치는 영향을 조사하였다. 배추종자의 발아와 초기생육에 있어 신규종자에서는 별효과가 없었으나 묵은 종자에서는 촉진효과가 있었고 그 적정 선량은 1.0Gy와 2.0Gy였다. 배추유식물체의 엽록소 함량은 저선량 조사구가 대조구보다 높았으며 조사선량의 증가에 따라 대체로 증가하였고, 저선량 조사에 의한 배추유식물체의 항산화효

Phytophthora capsici에 의한 고추 역병은 세계적으로 피해가 심할 뿐만 아니라 방제도 매우 어려운 병으로서 효과적인 병 방제를 위해 새로운 시도가 필요한 실정이다. 본 연구는 이러한 취지에서 감마선의 hormesis효과를 이용하고자 시도되었다. 저선량 감마선 조사가 고추의 역병 저항성을 유도하는지 여부를 밝히기 위해 광복과 다복 두 품종을 공시하였다. 저선량 감마선은 두 품종 모두 조사선량에 관계없이 발아율을 크게 제고시켰다. 병 저항성

저선량 방사선 조사가 땅콩 “팔팔” 품종 종자의 발아율과 초기생육 및 수량에 미치는 효과를 알아보고자 γ선을 0.5~20.0 Gy 까지 조사하여 포장에 직파재배하였다. 땅콩 종자의 발아율은 저선량 조사에 의해 별다른 효과가 없었으나 유묘초장은 저선량 조사구에서 다소 양호하였다. 수량구성요소 중협수와 종실수 및 종자수량은 12.0 Gy 조사구에서 가장 높았으며, 대조구에 비해 각각 27%와 17% 및 19% 유의성있게 증가하였다. 100립

저선량 방사선에 의한 식물 유익효과를 구명하기 위하여 2개 종묘회사로부터 4년간 묵은 종자를 분양받아 저수준의 γ선을 조사하여 온실과 포장에서 재배하여 그 생육 상황을 조사하였다. 서울종묘의 한여름배추는 0.5 Gy 조사구를 제외하고는 발아율 증대효과는 없었고 8 Gy와 12 Gy 조사구에서 유묘초장과 생체중이 각각 평균 20%와 40%정도 증가하여 초기생육 촉진효과는 있었으나 포장수량 증가 효과는 볼 수 없었다.

Currently, Japan is undertaking a nationwide project to measure and map radioactive contamination around Fukushima, as part of the efforts to restore normalcy following the nuclear accident. The Japan Atomic Energy Agency (JAEA) manages the Fukushima Environmental Safety Center, located approximately 20 km north of the Fukushima Daiichi nuclear power plant in Minamisōma City, Fukushima Prefecture. In collaboration with the JAEA, this study involved conducting comparison experiments and analyses with radiation detectors in high radiation environments, a challenging task in Korean environments. Environmental radiation surveys were conducted using three types of detectors: CZT, NaI(Tl), and LaBr3(Ce), across two contaminated areas. Dose rate values were converted using dose rate conversion factors for each detector type, and dose rate maps were subsequently created and compared. The detectors yielded similar results, demonstrating their feasibility and reliability in high radiation environments. The findings of this study are expected to be a crucial reference for enhancing the verification and supplementation of procedures and methods in future radiation measurements and mobile surveys in high-radiation environments, using these three types of radiation instruments.

The Korea Atomic Energy Research Institute operates the Nuclear Cycle Experimental Research Facility which has radiation controlled area in the laboratory with the aim of realizing pyroprocessing technology. In this Facility, depleted Uranium feed material and a depleted Uranium mixed with some surrogate material are used for performing experiments. Therefore the facility is using uranium, users should be careful of radiation. This paper will explain the radiation protection of the Nuclear Cycle Experimental Research facility and will also explain how much alpha radiation comes out from the facility. The RMS (Radiation Monitoring System) detector is made by CANBERRA and the model name is ICAM. ICAM RMS is the detector which can detect Alpha Radiation by absorbing the air in the facility. The RMS detector is installed in the HVAC room on the third floor to check the air contamination through the chimney. The RMS is connected to the air ventilation line for detecting Alpha radiation in the whole facility. Experiment was performed for two weeks to check the radiation level and the air ventilation fan continued to operate 24 hours a day. the results are below the required value which is 0.1 Bq/m3, indicating that the facility is safe in terms of radiation safety management.

The IAEA recommended considerations for exemption regulations of consumer products containing greater amounts of radioactive isotopes than the amounts specified for generic exemption. One of the major considerations is the expected exposure dose should be less than 10 μSv/y and 1 mSv/y for general cases and low probability cases, respectively, in all predictable scenarios. Under this recommendation, many countries evaluated the radiation dose for exposure scenarios of various products in consideration of the national circumstances and, then, established their own specific exemption regulation. In Republic of Korea, the “Regulation on substances excluded from radioactive isotopes” was legislated to specify consumer products excluded from regulation. However, as the usage status and product specifications has changed over time, it is necessary to periodically verify the validity of the regulation criteria in the view of exemption justification. In this study, we developed the use and disposal scenarios in consideration of the domestic use of thorium-containing gas mantle and evaluated radiation dose of each scenario accordingly. The gas mantles are used as a wick for gas lanterns and the maximum activity of natural thorium contained among the currently available gas mantles is 12.5 kBq. Radioactive isotopes in the decay chain of natural thorium can be divided into three groups according to their physical characteristics, and exposure routes suitable for each group were considered in dose calculation. Currently, most gas mantles are installed in camping lanterns. Therefore, we developed use scenarios related to camping. The average number of camping trips and time spent at the campground were set by the data from Korea Tourism Organization. Tent sizes and vehicle specifications were determined by referring to surveys and products in Korea. The used gas mantle is disposed of in a garbage bag for general waste and transported to landfill or incinerator. We determined the amount of gas mantle discarded in landfill and incinerator by the data from Korea Environment Corporation. The exposure time and amount handled by an individual were determined by considering the number of waste collection vehicles, landfills, and incinerators. Although we assumed the maximum activity of the gas mantle for conservative evaluation, the calculated radiation doses for the use and disposal scenarios were below the general requirement (i.e., 10 μSv/y) in all scenarios.

In general, dose assessment must be performed to obtain approval for clearance of radioactive waste. If the annual dose criteria through dose evaluation satisfies the clearance condition, radioactive waste can be disposed of. Various programs are used to perform dose assessment. NRCDOSE GASPAR is used as a program to assess the amount of radiation exposed to atmospheric emissions. Program is easy to use and results can be checked immediately after execution. GASPAR requires main input factors by exposure route such as site specifics, source term, special location, block data. Basically, program has default input values but user can easily modify it. The most important factor is that when entering a nuclide, the effect on progeny radionuclides is not automatically calculated. User should consider the dose contribution from progeny radionuclides. In this study, dose assessment was performed for combustible waste incineration using NRCDOSE GASPAR. And it was confirmed that exposure dose of individuals and groups criteria for clearance regulation.