• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2606-2613
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• 2022

Spent resin often exceeds radiation limits for safe disposal, creating a need for commercial-scale treatment techniques to reduce resin radioactivity. In this study, the radiological safety of a commercialized spent resin treatment device with a treatment capacity of 1 ton/day was evaluated. The results confirm that the device is radiologically safe in the event of an accident. This device desorbs ¹⁴C from the spent resin, allowing disposal as low-level waste instead of intermediate-level waste. The device also reduces overall waste by recycling the extracted ¹⁴C. Potential accident scenarios were explored to enable dose assessments for both internal and external exposure while preventing further spillage of the device and processing the spilled resin. The scenarios involved the development of a surface fracture on the resin mixture separator and microwave systems, which were operated under pressure and temperature of 0-6 bar and 0-150 ℃, respectively. In the case of accidents with separator and microwave device, the maximum allowable working time of worker were derived, respectively, considering external and internal exposures. When wearing the respirator corresponding to APF 50, in the case of the microwave device accident scenario, the radiological safety was confirmed when the maximum worker worked within 132.1 h.

• 대한핵의학회지
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• 제29권3호
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• pp.343-349
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• 1995

배경 : 방사선 외부 피폭에 대한 생물학적 선량측정방법에는 혈액학적 지표인 림프구 변화와 세포유전학적 지표인 염색체 분석을 통한 Ydr값이 가장 많이 사용되고 있다. 방사성 옥소 투여시와 같은 방사선 내부 피폭에 대해서는 생물학적 선량측정 방법에 대한 연구가 미흡하여 피폭정도는 물론 방사성 옥소 투여용량을 반영할 수 있는지의 여부도 알려져 있지 못하다. 목적 : 갑상선 질환자에게 방사성 옥소 투여후 림프구 변화와 Ydr값을 추적관찰하여 이들을 방사선 내부 피폭에 대한 지표로 이용할 수 있는지 알아보고자 하였다. 방법 : 갑상선 기능항진증 5명과 갑상선암 수술을 받은 35명의 환자를 대상으로 방사성 옥소 투여후 말초혈액 림프구 수를 2개원이상 추적검사 하였고, 림프구의 염색체 분석을 통해 Ydr값을 구했다. 결과: 1) 림프구 수는 방사성 옥소 투여 2주후 부터 감소되기 시작하여 6주와 8주후에 최대로 감소된후 점차 회복되었다. 2) 방사성 옥소량이 증가할 수록 림프구 수는 감소했다 (P<0.01) 3) Ydr값은 2주-8주 사이에는 대체로 일정하였다. 4) 방사성옥소 투여량에 따른 최대 Ydr값의 변화는 유의한 상관관계를 보였다 (p<0.00) 5) 2주째 Ydr값은 방사성옥소 투여량이 증가할 수록 증가하였다 (p<0.00) 6) 2주째 Ydr값은 2주째 림프구 수의 감소정도와 비례관계를 보였다 (p<0.00) 결론: 1) 방사성 옥소의 통상적 치료용량은 일시적 골수부전과 경도의 염색체이상을 초래하므로 8주 이상의 면밀한 추적관찰이 요구된다. 2) 생물학적 선량측정 방법으로서의 최대 림프구 감소치와 2주째 Ydr값과 최대 Ydr값은 방사성옥소 투여용량을 반영하는 지표로 사용할 수 있다.

• Nuclear Engineering and Technology
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• 제56권6호
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• pp.2050-2056
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• 2024

Handling of radioisotopes may cause external and internal contamination to occupational workers while using radiation for medical purposes. This research aims to monitor the internal hazard of occupational workers who handle ¹³¹I. Two methods are used: in vivo or direct method and in vitro or indirect method. The in vivo or direct method was performed by assessing thyroid intake with a thyroid uptake monitoring machine. The in vitro or indirect method was performed by assessing urine samples with the help of a gamma-ray spectroscopy practice using a High-Purity Germanium (HPGe) Detector. In this study, fifty-nine thyroid counts and fifty-nine urine samples were collected from seven occupational workers who were in charge of ¹³¹I at the National Institute of Nuclear Medicine and Allied Sciences (NINMAS), Dhaka. The result showed that the average annual effective dose of seven workforces from thyroid counts were 0.0208 mSv/y, 0.0180 mSv/y, 0.0135 mSv/y, 0.0169 m Sv/y, 0.0072 mSv/y, 0.0181 mSv/y, 0.0164 mSv/y and in urine samples 0.0832 mSv/y, 0.0770 mSv/y, 0.0732 mSv/y, 0.0693 mSv/y, 0.0715 mSv/y, 0.0662 mSv/y, 0.0708 mSv/y.The total annual effective dose (in vivo and in vitro method) was found among seven workers in average 0.1039 mSv/y, 0.0950 mSv/y, 0.0868 mSv/y, 0.0862 mSv/y, 0.0787 mSv/y, 0.0843 mSv/y, 0.0872 mSv/y. Following the rules of the International Commission on Radiological Protection (ICRP), the annual limit of effective dose for occupational exposure is 20 mSv per year and the finding values from this research work are lesser than this safety boundary.

• Journal of Radiation Protection and Research
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• 제34권4호
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• pp.184-189
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• 2009

중수로원전의 방사선작업종사자는 방사선작업 종료 후에 뇨시료를 제출하여 공기중 삼중수소의 섭취에 따른 내부피폭 선량을 평가하고 있다. 이 경우 종사자가 제출한 뇨시료는 삼중수소가 체내에서 평형에 도달한 대표시료(Representative sample)라는 전제를 필요로 한다. 국제방사선방호위원회(ICRP)의 간행물과 삼중수소의 인체평형에 대한 캐나다의 실험결과에 의하면 체내로 유입된 삼중수소는 약 2-3시간 후에 평형에 도달한다고 기술하고 있다. 그런데 원전에서는 계획예방정비기간 동안 일시에 많은 작업이 진행되고 빈번한 종사자의 출입으로, 방사선작업 종료 후 제출하는 뇨시료는 섭취 후 평형에 도달하는 약 2시간 경과 이전에 제출하거나, 지연하여 제출하는 경우가 발생할 수 있다. 따라서 이 논문에서는 방사선작업 종료 후 종사자가 제출하는 시간대별 뇨시료 중의 삼중수소 농도를 측정하였고, 이를 근거로 체내 삼중수소의 농도에 대한 변화추이와 선량평가에 미치는 영향을 분석하였다. 그 결과 종사자의 뇨시료는 대부분 삼중수소 섭취 후 2시간 정도에 신체 내에서 평형에 도달하는 것으로 확인되었다.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1757-1762
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• 2023

Radiological hazards from external exposure of naturally occurring radioactive materials (NORM) scales residues, generated during the extraction process of oil and gas production in southern Algeria, are evaluated. The activity concentrations of ²²⁶Ra, ²³²Th, and ⁴⁰K were measured using high-purity gamma-ray spectrometry (GeHP). Mean activity concentration of ²²⁶Ra, ²³²Th and ⁴⁰K, found in scale samples are 4082 ± 41, 1060 ± 38 and 568 ± 36 Bq kg^-1, respectively. Radiological hazard parameters, such as radium equivalent (Ra_eq), external and internal hazard indices (H_ex, H_in), and gamma index (I_γ) are also evaluated. All hazard parameter values were greater than the permissible and recommended limits and the average annual effective dose value exceeded the dose constraint (0.3 mSv y^-1). However, for occasionally exposed workers, the dose rate of 0.65 ± 0.02 mSv y^-1 is lower than recommended limit of 1 mSv y^-1 for public.

• 방사선산업학회지
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• 제18권2호
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• pp.147-153
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• 2024

Radioactive liquid waste generated during operation and overhaul is collected and reused through the radioactive liquid waste treatment system and continuous monitoring system in the nuclear power plant or discharged to the outside if it satisfies the limit within the control and monitoring. However, there are concerns about boric acid management, which controls the power output of nuclear power plants in radioactive liquid waste. Due to the behavior of boric acid, it is difficult to remove it in the existing liquid radwaste system, and the concentration of boric acid water discharged tends to be higher than the natural state of 5 ppm, so additional facilities should be considered. Therefore, this study aims to evaluate the radiological effects of radioactive waste treatment facilities that are under development and use them as a basis for managing worker exposure and evaluating the safety of facilities in the future.

• 한국방사선학회논문지
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• 제12권3호
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• pp.329-334
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• 2018

라돈은 자연방사성원소로 호흡을 통해 인체에 피폭된다. 본 연구에서는 2017년 6월 1일부터 2017년 8월 28일까지 3개월 동안 A대학의 8개 건축물에 대해 실내 라돈농도를 측정하여 비교하였고, 연간 유효선량을 도출하였다. 본 연구에서 A대학의 건축물 Hall G와 Hall F의 라돈농도는 각각 $81Bq/m^3$, $14Bq/m^3$로 나타났으며, 전체 조사 건축물의 평균 실내 라돈농도는 $41.63Bq/m^3$로 나타났다. 대학 내 학습공간과 생활공간에 대한 연간 유효선량 환산치의 평균은 0.40 mSv/y이며 최대 연간 유효선량은 0.78 mSv/y, 최소 연간 유효선량은 0.13 mSv/y로 나타났다. 학교는 학생들이 오랜 시간 머무르는 공간이므로 건축물에 대한 적절한 환기와 관리를 통해 실내라돈 농도를 낮추는 것이 라돈에 대한 자연방사선 피폭을 낮추는 방법이다.

• Journal of Radiation Protection and Research
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• 제27권2호
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• pp.121-126
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• 2002

본 연구는 지하수로부터 방출되어 가옥의 실내에 존재하는 라돈에 의한 체내축적량을 현실적으로 평가하는 방법을 보여준다. 먼저 지하수로부터 실내공기로 전달되는 과정을 모의하기 위해 2_구역모델을 개발하였다. 이 모델은 실내에서 발생하는 생활활동, 즉, 목욕, 세수, 세탁, 변기에서의 물사용에 의해 실내로 휘발, 이동하는 시간에 따를 라돈농도분포를 계산한다. 다음, 이 모델의 불확실성이 존재하는 입력인자들에 대해 불확실성분석을 수행하여 최종 실내라돈 농도분포를 결정하였다. 그리고 이러한 실내 라돈을 호흡하여 체내에 축적되는 양을 보다 정량적으로 모의하기 위해 PBPK 모델을 개발하였다. 불확실성이 포함된 라돈농도분포와 정량적인 체내축적모의를 위한 PBPK 모델의 결합으로 보다 현실적인 라돈의 체내축적량을 분석할 수 있다. 이러한 연구의 결과는 지하수로부터 발생하는 라돈에 의한 인체위해평가시 도움을 주리라고 판단된다.

• Journal of Radiation Protection and Research
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• 제45권1호
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• pp.2-10
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• 2020

Background: Huge amounts of radionuclides were released into the environment due to the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident, which caused not only serious contamination on the ground, but also radiation exposure to the public. One problem that remains in performing the dose estimation is the difficulty of estimating the internal thyroid dose due to the intake of radioiodine (mainly, ¹³¹I) because of limitations to the human data available. Materials and Methods: The relevant papers were collected and reviewed by the authors. The results of thyroid dose estimates from different studies were tabulated for comparison. Results and Discussion: The thyroid dose estimates from the studies varied widely. The dose estimates by the United Nations Scientific Committee on the Effects of Atomic Radiation were higher than the others due to the ingestion dose being based on conservative assumptions. The dose estimates by Japanese experts were mostly below 20-30 mSv. The recent studies suggested that exposure on March 12, 2011 would be crucial for late evacuees from the areas near the FD-NPP because of the possible intake of short-lived radionuclides other than ¹³¹I. Further multilateral studies are vital to reduce uncertainties in the present dose estimations. Conclusion: The estimation of the thyroid doses to Fukushima residents still has many uncertainties. However, it is considered unlikely that the thyroid doses exceeded 50 mSv except in some extreme cases. Further multilateral studies are thus necessary to reduce the uncertainties in the present dose estimations.

• Radiation Oncology Journal
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• 제37권4호
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• pp.259-264
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• 2019

Purpose: Accurate localization of the lumpectomy cavity during accelerated partial breast radiation (APBR) is essential for daily setup to ensure the prescribed dose encompasses the target and avoids unnecessary irradiation to surrounding normal tissues. Three-dimensional ultrasound (3D-US) allows direct visualization of the lumpectomy cavity without additional radiation exposure. The purpose of this study was to evaluate the feasibility of 3D-US in daily target localization for APBR. Materials and methods: Forty-seven patients with stage I breast cancer who underwent breast conserving surgery were treated with a 2-week course of APBR. Patients with visible lumpectomy cavities on high quality 3D-US images were included in this analysis. Prior to each treatment, X-ray and 3D-US images were acquired and compared to images from simulation to confirm accurate position and determine shifts. Volume change of the lumpectomy cavity was determined daily with 3D-US. Results: A total of 118 images of each modality from 12 eligible patients were analyzed. The average change in cavity volume was 7.8% (range, -24.1% to 14.4%) on 3D-US from simulation to the end-of-treatment. Based on 3D-US, significantly larger shifts were necessary compared to portal films in all three dimensions: anterior/posterior (p = 7E-11), left/right (p = 0.002), and superior/inferior (p = 0.004). Conclusion: Given that the lumpectomy cavity is not directly visible via X-ray images, accurate positioning may not be fully achieved by X-ray images. Therefore, when the lumpectomy cavity is visible on US, 3D-US can be considered as an alternative to X-ray imaging during daily positioning for selected patients treated with APBR, thus avoiding additional exposure to ionizing radiation.