• 치과방사선
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• 제18권1호
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• pp.31-45
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• 1988

The author studied the histopathologic changes according to a single or a split dose and the time after irradiation on the acinar cells of rat parotid gland. 99 Sprague Dawley rats, weighing about l20gm, were divided into control and 3 experimental groups. In experimental groups, GroupⅠ and Ⅱ were delivered a single dose of l5Gy, 18Gy and Group Ⅲ and Ⅳ were delivered two equal split doses of 9Gy, 10.5Gy for a 4 hours interval, respectively. The experimental groups were delivered by a cobalt-60 teletherapy unit with a dose rate of 222cGy/min, source-skin distance of 50㎝, depth of l㎝ and a field size of l2×5㎝. The animals were sacrificed at 1, 2, 3, 6, 12 hours, 1, 3, 7 days after irradiation and examined by light and electron microscopy. The results were as follows: 1. As the radiation dose increased and the acinar cells delivered a single dose exposure were more damaged, and the change of acinar cells appeared faster than those of a split dose exposure. 2. The histopathologic change of acinar cells appeared at 1 hour after irradiation. The recovery from damaged acinar cells appeared at 1 day after irradiation and there was a tendency that the recovery from damage of a split dose exposure was somewhat later than that of a single dose exposure. 3. Light microscope showed atrophic change of acinar cells and nucleus, degeneration and vesicle formation of cytoplasm, widening of intercellular space and interlobular space. 4. Electron microscope showed loss of nuclear membrane, degeneration of nucleus and nucleoli, clumping of cytoplasm, widening and degeneration of rough endoplasmic reticulum, loss of cristae of mitochondria, lysosome, autophagosome and lipid droplet. 5. Electron microscopically, the change of rough endoplasmic reticulum was the most prominent and this appeared at 1 hour after irradiation as early changes of acinar cells. The nuclear change appeared at 2 hours after irradiation and the loss of cristae of mitochondria was observed at 2 hours after irradiation in all experimental groups.

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1225-1233
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• 2024

Level 3 probabilistic safety assessment (PSA) is performed to calculate radionuclide concentrations and exposure dose resulting from nuclear power plant accidents. To calculate the external exposure dose from the released radioactive materials, the radionuclide concentrations are multiplied by two factors of dose coefficient and a finite cloud dose correction factor (FCDCF), and the obtained values are summed. This indicates that a standard set of FCDCFs is required for external exposure dose calculations. To calculate a standard set of FCDCFs, the effective distance from the release point to the receptor along the wind direction should be predetermined. The TID-24190 document published in 1968 provides equations to calculate FCDCFs and the resultant standard set of FCDCFs. However, it does not provide any explanation on the effective distance required to calculate the standard set of FCDCFs. In 2021, Sandia National Laboratories (SNLs) proposed a method to predetermine finite effective distances depending on the atmospheric stability classes A to F, which results in six standard sets of FCDCFs. Meanwhile, independently of the SNLs, the authors of this paper discovered that an infinite effective distance assumption is a very reasonable approach to calculate one standard set of FCDCFs, and they implemented it into the multi-unit radiological consequence calculator (MURCC) code, which is a post-processor of the level 3 PSA codes. This paper calculates and compares short- and long-range FCDCFs calculated using the TID-24190, SNLs method, and MURCC method, and explains the strength of the MURCC method over the SNLs method. Although six standard sets of FCDCFs are required by the SNLs method, one standard sets of FCDCFs are sufficient by the MURCC method. Additionally, the use of the MURCC method and its resultant FCDCFs for level 3 PSA was strongly recommended.

• Environmental Analysis Health and Toxicology
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• 제18권4호
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• pp.237-242
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• 2003

Single cell gel electrophoresis (SCGE) was used to the experiment with the variation on the amount of smoking and low dose radiation exposure to find how much the Lymphocyte DNA was damaged, and especially for whom smoke a lot(about 20 or more than 20 cigarettes a day) it was found to be highly damaged. While, the damage of 'not more than 20 cigarettes a day' was found to be not so much significant as like for whom smoke about or more than 20 cigarettes a day And, according to the different amount of the radiation exposure, the Lymphocyte DNA was found to be considerably damaged for 0-13m Sv (P<0.01), it was not able to prove the relationship between the DNA damage and the radiation exposure.

• Nuclear Engineering and Technology
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• 제53권6호
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• pp.2019-2024
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• 2021

For evaluating the radiological safety of dismantled concrete, the process of disposal and recycling of the radioactive concrete generated during the dismantling of Kori Unit 1 is analyzed. Four scenarios are derived based on the analysis of the concrete recycling and disposal process, and the potential exposure to the workers and public during this process are calculated. VISIPLAN and RESRAD code are used for evaluating the dosages received by the workers and public in the following four scenarios: concrete inspection, transport of concrete by the truck driver, driving on a recycled concrete road, and public living near the landfilled concrete waste. Two worker exposure scenarios in the processing of concrete and two public exposure scenarios in recycling and disposal are considered; in all the scenarios, the exposure dose does not exceed the annual dose limit for each representative.

• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2652-2660
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• 2021

The gamma-ray exposure doses in decontamination operation after a nuclear accident were evaluated with a consideration of various geometrical conditions and specific gamma-ray energies. The calculation domain is organized with three residence types and each form is divided into two kinds of geometrical arrangements. The position-wise air KERMA values were calculated with an assumption of evenly distributed gamma-ray source based on Monte Carlo radiation transport analysis using the MCNP code. The radioactivity is initially set to be unity to be multiplied by the deposition value measured in the actual accident condition. The workforce data set depending on the target object was determined by modifying the Fukushima report. The external exposure doses for decontamination workers were derived from the calculated KERMA values and the workforce analysis. These results can be used to efficiently determine the workforce required by the characteristics of the area and the structure to be decontaminated within the dose limits.

• Journal of Radiation Protection and Research
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• 제39권3호
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• pp.142-149
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• 2014

한국은 국가건강검진을 시행하여 국민건강증진에 크게 기여하고 있으며 그 수검률 또한 증가하고 있다. 본 연구는 수검률 증가에 따른 방사선검사의 증가가 예상되어 그 이용 빈도(이용량)와 피폭선량을 파악하고자 한다. 본 연구는 2011년 국민건강보험공단 건강검진 분석 자료에서 방사선검사를 분리하여 이용량을 파악하고, UNSCEAR 2008년 보고서의 수록되어 있는 검사별 선량을 적용하여 국가건강검진에서 방사선검사로 인한 피폭선량을 추정한다. 주요 분석결과 2011년 국가건강검진 수검자 1인당 평균 피폭선량은 0.57 mSv로 추정되었고, 최대 11.081 mSv, 최소 0.02 mSv로 추정되었다. 방사선검사의 이용 빈도와 피폭선량은 각각 총 16,005,914건, 6,311.76 person-Sv로, 이중 이용량은 흉부 X선검사가 1,070,569 (69.17%)건으로 가장 높았고, 피폭선량은 위장조영검사가 5,217.94 (82.67%) person-Sv로 가장 높았다. 성 연령별 결과 39세 이하를 제외한 전 연령대에서 여성의 수검비율과 피폭선량이 높았고, 특히 50-54세 여성이 1,674,787 (10.5%)건, 701.59 (11.1%) person-Sv로 가장 높았다. 검사별 선량에서 위장조영검사가 전체 82.67%를 차지하는 만큼 의료상(목적) 반드시 시행하는 경우를 제외하고는 위장내시경검사를 선택하여 수검 받도록 정책적으로 장려하고 외국의 사례와 같이 경제성과 실효성 평가에 따라 폐지된다면 국가건강검진에의 방사선피폭은 현저히 줄어들 것으로 예상한다.

• 핵의학기술
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• 제13권1호
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• pp.93-97
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• 2009

2006년~2008년 2사분기까지의 2.5년간의 환자 건수는 14,674건이었으며, $^{18}F$-FDG 평균 주사량은 461.5 MBq 였다. 2.5년간 순환근무는 3회 이루어졌고, 10명의 방사선사 중 PET과 Gamma 영역별 1인을 제외한 8명의 순환근무가 시행되었다. 추가로 2008년 3인의 신입인력이 야간에 투입되어 이에 대한 평가도 이루어졌다. 방사선사의 근무연한은 15년 이상이 2인, 10~15년이 3인, 5~10년이 1인, 5년 미만이 3인이었다. 이들의 개인별 피폭선량은 먼저 PET실에 근무를 하고 있을 때가 Gamma 영역에 근무하고 있을 때 보다 더 높게 나왔다. 가장 큰 원인으로는 일일 처리 건수 면에서 PET과 Gamma영역의 차이가 거의 없는 상태에서 $^{99m}Tc$보다는 상대적으로 에너지가 높은 $^{18}F$-FDG를 사용하는데 있다고 본다. 특히 개인별 피폭선량도 근무연한에 따른 분기별 평가에서 서로 다르게 나타났다. 또한 순환근무 초기 1개월째보다는 업무의 연속성을 익힌 3개월째에 더 낮은 피폭선량을 보여 주고 있다. 이는 PET 실의 근무연한이 길수록 업무의 숙달도가 증가하여 개인별 피폭선량은 감소하는 것으로 보인다. 예약실에 근무하는 간호사의 피폭선량은 $^{18}F$-FDG 주사 후 짧은 시간에 환자와의 접촉이 이루어지고 있어 그리 큰 문제점을 보이지는 않았다. 그러나 임신 가능성이 있는 간호사일 경우는 이를 재고해 보아야할 필요가 있다. 순환 근무를 통한 장시간 PET/CT실을 벗어난 상황이 될 경우 대부분의 근무자가 초기 1개월에서 업무의 연속성 결여 및 개인별 피폭선량 증가라는 위험성을 내포하였다. PET/CT 환자의 증가에 따른 PET/CT실 전체의 과도한 피폭을 분산하기 위한 순환 근무제의 도입이 또 다른 문제점을 갖고 있음을 알 수 있다.5,6) 이를 해결하기 위해서는 근무자의 업무재교육과 순환 및 고정 근무제의 적절한 병행을 시행할 필요가 있다고 본다. 또한 고정 근무자는 순환 근무 인력들의 이런 문제점을 해결하기 위해 업무영역에서 표준화된 업무지침서 등을 만들어야 한다.

• Nuclear Engineering and Technology
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• 제30권4호
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• pp.308-317
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• 1998

Ensuring occupational radiation exposure(ORE) as low as is reasonably achievable(ALARA) has been one of very important requirements in a nuclear power plant. It is well known that about 70 percent of occupational dose has incurred from maintenance jobs in the outage period. To reduce occupational dose effectively, the high-dose jobs in the outage period should be identified with their dose reduction potentials and methods. In this study, a PC-based ORE database program, INSTORE, is developed to evaluate ORE doses in individual jobs, and the ORE data of Kori Units 3 and 4 are assembled to the database. Based on customary job classification, radiation work is classified into 26 main jobs which comprise 61 detailed jobs, and occupational doses are assessed according to each detailed job. As a result, high-dose jobs are identified with dose reduction priority in terms of collective ORE dose. It is recommended that adeqaute dose reduction methods for these jobs should be prepared to improve their working conditions and procedures.

• 대한방사선기술학회지:방사선기술과학
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• 제19권2호
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• pp.59-65
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• 1996

We studied exposure techniques and exposure dose for simple abdomen A-P projection for 41 medical facilities that are located in Seoul area. 1. The range of tube voltage used was 60 to 84 kVp, the average tube voltage used was 74 kVp 2. Only 17% of added filter was used. 3. Tube current mostly used was 200 mA, some of them used 400 mA. 4. The grid ratio mostly was used 10 : 1, 54 % of the rare earth screen was used in most facilities. 5. The average skin entrance dose was 4.15 mSv and the dose range was 1.05 mSv to 11.0 mSv.

• 대한방사선협회지
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• 제27권2호
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• pp.57-65
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• 2001

본 연구는 복부 단순 X선 검사시 발생하는 피폭선량에 대하여 실험을 수행하였다. 피폭선량을 심부선량 백분율,표면선량,산란선량율으로 각각 측정하였다. 그결과는 다음과 같았다. 1. 관전압이 $60\～85kV$증가시 표면선량은 증가하고, 촬영거리를 50\～150cm$로 20cm씩 증가함에 mAs도 증가시킨 결과 표면선량은 감소되었다. 2. 심부선량 백분율은 $60kV\～75kV$에서는 4cm깊이에서