• Title/Summary/Keyword: Exposure Dose

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Planning of Optimal Work Path for Minimizing Exposure Dose During Radiation Work in Radwaste Storage (방사성 폐기물 저장시설에서의 방사선 작업 중 피폭선량 최소화를 위한 최적 작업경로 계획)

  • Park, Won-Man;Kim, Kyung-Soo;Whang, Joo-Ho
    • Journal of Radiation Protection and Research
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    • v.30 no.1
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    • pp.17-25
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    • 2005
  • Since the safety of nuclear power plant has been becoming a big social issue the exposure dose of radiation for workers has been one of the important factors concerning the safety problem. The existing calculation methods of radiation dose used in the planning of radiation work assume that dose rate does not depend on the location within a work space thus the variation of exposure dose by different work path is not considered. In this study, a modified numerical method was presented to estimate the exposure dose during radiation work in radwaste storage considering the effects of the distance between a worker and sources. And a new numerical algorithm was suggested to search the optimal work path minimizing the exposure dose in pre-defined work space with given radiation sources. Finally, a virtual work simulation program was developed to visualize the exposure dose of radiation doting radiation works in radwaste storage and provide the capability of simulation for work planning. As a numerical example, a test radiation work was simulated under given space and two radiation sources, and the suggested optimal work path was compared with three predefined work paths. The optimal work path obtained in the study could reduce the exposure dose for the given test work. Based on the results, tile developed numerical method and simulation program could be useful tools in the planning of radiation work.

Study on the Exposure Field of Head and Neck with Measurement of X-ray dose Distribution for Dental Panoramic X-ray System (치과 파노라마 장치의 X선 공간선량분포 측정을 통한 두경부 피폭영역 조사에 대한 연구)

  • Oh, Yoonjin;Hong, Girang;Lee, Samyol
    • Journal of the Korean Society of Radiology
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    • v.9 no.1
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    • pp.17-21
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    • 2015
  • Recently, As people's interest in the health of teeth is increased in the medical field changed into aging society, the number of times for the radiological diagnosis is increased. It can be said that the radiation exposure dose of Korean population is increased. It is also growing concern about radiation exposure. Therefore, the basic data for the dental panoramic X-ray system, its investigation and measuring the radiation dose is needed. In this study, we used ALOKA PDM-117 dosimeter and estimated a two-dimensional dose distribution of the dental panoramic X-ray system (VATEC Pax-400). Dose evaluation about the distribution is confirmed from the point of radiation exposure of a patient. Dose distribution of the dental panoramic X-ray system irradiated chin and the facial region to high dose as well as the parts of teeth. It was founded that the eye lens which are sensitive to radiation are exposed to unnecessary radiation, considering the effect of scattered radiation. The results of this study will be used more accurate dose assessment in a variety of object size and location of measuring dose.

A Study on Retrospective of External Radiation Exposure Dose by Optically Stimulated Luminescence of Smart Chip Card (스마트칩 카드을 이용한 광 자극 발광 특성 연구)

  • Park, Sang-Won;Yoo, Se-Jong
    • Journal of radiological science and technology
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    • v.42 no.5
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    • pp.379-385
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    • 2019
  • Radiation is used for various purposes such as cancer therapy, research of industrial and drugs. However, in case of radiation accidents such as terrorism, collapsing nuclear plant by natural disasters like Fukushima in 2011, very high radiation does expose to human and could lead to death. For this reason, many people are concerning about radiation exposures. Therefore, assessment and research of retrospective radiation dose to human by various path is an necessary task to be continuously developed. Radiation exposure for workers in radiation fields can be generally measured using a personal exposure dosimeter such as TLD, OSLD. However, general people can't be measured radiation doses when they are exposed to radiation. And even if radiation fields workers, when they do not in possession personal dosimeter, they also can't be measured exposure dose immediately. In this study, we conduct retrospective research on reconstruction of dose after exposure by using smart chip card of personal items through Optically Stimulated Luminescence (OSL). The OSL signal of smart chip card shows linear response from 0.06 Gy to 15 Gy and results of fading rate 45 %, 48% for 24 and 48 hours due to the natural emission of radiation in sample, respectively. The minimum detectable limit (MDD) was 0.38 mGy. This values are expected to use as correction values for reconstruction of exposure dose.

Study on the Effectiveness of Radiological Technologist's Thyroid Shielding in Pediatric Paranasal Sinus X-ray Examination (어린이 부비동 엑스선 검사에서 검사자의 갑상선 차폐 효과성에 관한 연구)

  • Chang-Kyo Kwak;Jeong-Taek Kwon;Kwang-Je Lee;Il-Hwan Bae;Hye-Jung Kim;So-Mi Lee;Do-Byung Rhee
    • Journal of radiological science and technology
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    • v.47 no.3
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    • pp.197-203
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    • 2024
  • During paranasal sinus X-ray examinations in children, the radiological technologist's thyroid shield is often not implemented to shorten the examination time. This study measured the radiation exposure before and after the implementation of thyroid shielding by analyzing the difference in radiation exposure, the radiological technologist's could receive depending on the actual thyroid shielding. In the left TLD, when thyroid shielding was not performed(N), the radiation exposure dose(mSv) was 2.869 for the depth dose[Hp(10)] and 2.886 for the surface dose[H(3)], and when thyroid shielding was performed(Y), the Hp(10) was 0.033 and the H(3) was 0.034. In the right TLD, when thyroid shielding was not performed(N), the radiation exposure dose was 3.149 for Hp(10) and 3.137 for H(3), and when thyroid shielding was performed, the Hp(10) of (Y) was 0.013 and the H(3) was 0.015. The differences in the overall exposure dose measurement values are all statistically significant (p<0.05). The difference in radiation dose between when thyroid shielding was not performed and when thyroid shielding was performed was more than 99.2% in both cases, indicating a high radiation shielding rate.

X-선 발생장치 정류방식에 따른 출력특성에 관한 연구

  • Na, Gil-Ju;Baek, Su-Ung;Yang, Hyeon-Hun;Park, Gye-Chun
    • Proceedings of the Korean Institute of Electrical and Electronic Material Engineers Conference
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    • 2009.11a
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    • pp.126-126
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    • 2009
  • X-ray high-voltage generator is the most important part that can decide the radiation exposure dose affecting a patient or operator according to the characteristic. If decrease of X-ray radiation exposure dose and output characteristic of high-voltage generator is unstable, a patient or operator must be exposed to more radiation. This study measures and analyzes the exposure dose reproducibility and output characteristic according to a change of tube current on the various rectification methods of diagnostic X-ray equipment. It can find that quality bastardize and output is increased if voltage of X-ray tube is increased. Exposure dose reproducibility according to output of X-ray equipment is extremely excellent in inverter type, and is stable in order of following three-phase, a single-phase and condenser method. This study can find that the reply incidence of high-voltage generator is generated due to difference in rectification method, noise occurs in X-ray due to that, quality of an image is decreased due to that, and medical diagnosis can be failed due to that.

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The Study on Scattered Ray by C-arm in Operation Room (수술실 내 C-arm 장치의 산란선 분포에 대한 연구)

  • Park, Seung-Hyun;Park, Joo-Mi;Kim, Hyun-Soo
    • Korean Journal of Digital Imaging in Medicine
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    • v.13 no.1
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    • pp.21-26
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    • 2011
  • A radiation imaging system used in a surgery room is mainly using C-arm which is purposed to fluoroscope. C-arm is often use to watch an operation's accuracy and progress, but not only being bombed to this first beam but also affected to this scattered beam, so now we are look for the way to reduce bombed amount of doctor, nurses and radiological technologists. We measured the exposure dose in $0^{\circ}$ spot according to the distance to find out frequency distribution of scattered ray in an operation room and found the spot which has the same exposure dose from $30^{\circ}$ distance of all directions and wrote isodose curve. We analyzed the data and found out the sudden reduction of scattered ray according to the long direction also found out that scattered ray was not related to the directions. Operators must recognize the reduction of exposure dose. Because reducing scattered ray from all directions in an operation room is really difficult. So every operators must use shelters to reduce the exposure dose and notice the safety.

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Preliminary Evaluation of Radiological Impact for Domestic On-road Transportation of Decommissioning Waste of Kori Unit 1

  • Dho, Ho-Seog;Seo, Myung-Hwan;Kim, Rin-Ah;Kim, Tae-Man;Cho, Chun-Hyung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.18 no.4
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    • pp.537-548
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    • 2020
  • Currently, radioactive waste for disposal has been restricted to low and intermediate level radioactive waste generated during operation of nuclear power plants, and these radioactive wastes were managed and disposed of the 200 L and 320 L of steel drums. However, it is expected that it will be difficult to manage a large amount of decommissioning waste of the Kori unit 1 with the existing drums and transportation containers. Accordingly, the KORAD is currently developing various and large-sized containers for packaging, transportation, and disposal of decommissioning waste. In this study, the radiation exposure doses of workers and the public were evaluated using RADTRAN computational analysis code in case of the domestic on-road transportation of new package and transportation containers under development. The results were compared with the domestic annual dose limit. In addition, the sensitivity of the expected exposure dose according to the change in the leakage rate of radionuclides in the waste packaging was evaluated. As a result of the evaluation, it was confirmed that the exposure dose under normal and accident condition was less than the domestic annual exposure dose limit. However, in the case of a number of loading and unloading operations, working systems should be prepared to reduce the exposure of workers.

Estimation of Human Carcinogenic Potency (HCP) of Carcinogens in Risk Assessment and Management. (위해성 평가 및 관리에 있어서 발암물질의 인체발암능력 평가)

  • 이병무;김대영;김세기;김근종
    • Environmental Mutagens and Carcinogens
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    • v.19 no.1
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    • pp.39-45
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    • 1999
  • Human Carcinogenic Potency (HCP) can be estimated based on human daily exposure dose to carcinogen (Dh), body weight (Wh), 10% tumorigenic dose (TD10), and slope factor at TD10 (Q10) from 2-yr bioassay data. This approach is more relevant to humans generally exposed to low doses of carcinogens and can reduce more of extrapolation errors from high dose in animal experiments to low dose in humans than HERP (human exposure dose/rodent potency dose) proposed by Ames et al. (Science, 236, 271-280, 1987). TD50 and HERP have been routinely used to compare rodent carcinogenic potency and human carcinogenic potency, but those approaches have had limitations in extrapolation of high dose to low dose in humans. The advantages of HCP are to estimate human exposure dose (Dh) by human monitoring instead of environmental monitoring, to consider slope factor (Q10) which reflects the tendency of curve at low dose, and to use TD10 which represents much lower dose thant TD50 or HERP. HCP will be a useful parameter for the estimation of human carcinogenic potency in risk assessment and management of carcinogens.

Radiological safety assessment of lead shielded spent resin treatment facility with the treatment capacity of 1 ton/day

  • Byun, Jaehoon;Choi, Woo Nyun;Kim, Hee Reyoung
    • Nuclear Engineering and Technology
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    • v.53 no.1
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    • pp.273-281
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    • 2021
  • The radiological safety of the spent resin treatment facility with a14C treatment capacity of 1 ton/day was evaluated in terms of the external and internal exposure of worker according to operation scenario. In terms of external dose, the annual dose for close work for 1 h/day at a distance of more than 1 m (19.8 mSv) satisfied the annual dose limit. For 8 h of close work per day, the annual dose exceeded the dose limit. For remote work of 2000 h/year, the annual dose was 14.4 mSv. Lead shielding was considered to reduce exposure dose, and the highest annual dose during close work for 1 h/day corresponded to 6.75 mSv. For close work of 2000 h/year and lead thickness exceeding 1.5 cm, the highest value of annual dose was derived as 13.2 mSv. In terms of internal exposure, the initial year dose was estimated to be 1.14E+03 mSv when conservatively 100% of the nuclides were assumed to leak. The allowable outflow rate was derived as 7.77E-02% and 2.00E-01% for the average limit of 20 mSv and the maximum limit of 50 mSv, respectively, where the annual replacement of the worker was required for 50 mSv.

Investigation on Evaluation of Exposure Dose & Radiographic Technique for Diagnostic X-ray Examination (X선검진시의 촬영조건과 피폭선량 평가에 대한 조사)

  • Kim Kyung Hwan;Lee Jin Kyu
    • Journal of The Korean Radiological Technologist Association
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    • v.27 no.2
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    • pp.229-251
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    • 2001
  • At the investigations with 200 institutes for analysis of factor associated with radiographic conditions reduction of patient exposure dose during X-ray diagnosis, 170 institutes or $85\%$ answered. For estimation of exposure dose the entrance

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