• Journal of Radiation Protection and Research
• /
• 제40권4호
• /
• pp.211-215
• /
• 2015

원자력사고 등의 방사선비상시 환경으로 누출된 방사성물질은 일반인의 내부피폭을 야기할 수 있다. 특히 감마선 방출핵종의 내부피폭의 경우 전신계수기가 널리 사용되지만 현장에서 신속히 내부피폭을 분류하는 용도로는 부적합하다. 본 연구에서는 휴대용 감마스펙트로메터를 비상시 내부피폭 신속분류에 적용하기 위하여 몬테카를로 전산모사 방법을 이용하여 NaI 검출기의 계측효율을 BOMAB 팬텀의 크기별로 평가하였다. 두 가지 측정 지오메트리에서 계측효율을 비교한 결과 앉은 모델에서의 계측효율이 서 있는 모델에 비해 약 1.1배 높은 계측효율을 나타내었다. 하지만 측정 지오메트리에 의한 계측효율 차이보다 신체크기에 따른 계측효율 차이가 크게 발생하는 것을 확인하였다. 특히 신체크기가 작은 4세 팬텀의 경우 표준남성과 비교하면 약 2.4~3.1배의 높은 계측효율을 나타내어 신체크기가 상이한 일반인을 대상으로 내부피폭을 모니터링할 경우 반드시 계측효율에 대한 고려가 필요한 것으로 확인되었다.

• 한국재료학회지
• /
• 제30권12호
• /
• pp.641-649
• /
• 2020

A facile microwave assisted solvothermal process is designed for fabricating SnS nanoparticles decorated on graphene nanosheet, which used as visible light driven photocatalyst. Some typical characterization techniques such as XRD, FT-IR, SEM with EDX analysis, and TEM and BET analysis are used to analyse the physical characteristics of as-prepared samples. Spherical SnS nanoparticles are uniformly dispersed on the surface of graphene nanosheet due to ammonia, which can prevent the aggregation of graphene oxide. Meanwhile, microwave radiation provides fast energy that promotes the formation of spherical SnS nanoparticles within a short time. The visible light photocatalytic activity of as-prepared SnS-GR nanocomposites is analysed through photodegradation efficiency of methylene blue with high concentration. According to the higher photocatalytic property, the as-prepared SnS-GR nanocomposites can be expected to be an efficient visible light driven photocatalyst. After five cycles for decolorization, the rate decreases from 87 % to 78 % (about 9 %). It is obvious that the photocatalytic activity of SnS-GR nanocomposite has good repeatability.

• Journal of Radiation Protection and Research
• /
• 제26권4호
• /
• pp.393-398
• /
• 2001

매년 병원에서 사용 후 폐기되는 비가연성 폐기물은 ${\gamma}$-선과 ${\beta}$-선을 방출하지만 방사능은 주변방사능 수준으로 매우 낮다. 이를 측정하기 위한 기존의 방법은 비효율적이고 복잡하므로, 좀더 간단한 방법이 긴요하다. 본 논문에서는 측정 방사선의 특성상 핵종에 따라 다른 측정방법을 사용하였는데, ${\gamma}$-선 방출 핵종은 표준시료로부터 효율곡선식을 도출하여 미지의 방사능을 측정하였다 ${\beta}$-선 방출 핵종은 Monte Carlo 시뮬레이션을 통해 계측 효율을 예측하고 표면장벽형계측기로 측정하여 미지의 방사능 양을 결정하는 새로운 방법을 제시하였다. 연구결과에 의하면 이론적 계산치와 표면장벽형 계측기를 이용하면 전처리를 필요로하는 액체섬광계수기를 이용하지 않고 또한 계측효율을 결정하기 위한 비경제적인 표준시료 측정시험과정 없이도 저에너지 방사선을 약 17% 오차 범위내에서 결정할 수 있다고 판단된다.

• Journal of Radiation Protection and Research
• /
• 제44권1호
• /
• pp.8-14
• /
• 2019

Background: Management of an agricultural food product system following a nuclear accident is indispensable for reducing radiation exposure due to ingestion of contaminated food. The present study analyzes the effect of agricultural countermeasures on ingestion dose following a nuclear accident. Materials and Methods: Agricultural countermeasures suitable for domestic farming environments were selected by referring to the countermeasures applied after the Fukushima accident in Japan. The avertable ingestion doses that could be obtained by implementing the selected countermeasures were calculated using the Korean Agricultural Countermeasure Analysis Program (K-ACAP) to investigate the efficiency of each countermeasure. Results and Discussion: Of the selected countermeasures, the management of crops was effective when radionuclide deposition occurred during the growing season of plants. Treatment by soil additive and topsoil removal was effective when deposition occurred during the nongrowing season of plants. The disposal of milk was not effective owing to the small contribution of milk to the overall ingestion dose. Clean feeding of livestock was effective when deposition occurred during the growing season of fodder plants such as pasture and rice-straw. Finally, the effect of food restriction increased with the soil deposition density of radionuclide. The practical effect of countermeasures was very small when the avertable ingestion dose was absolutely low. Conclusion: The agricultural countermeasures selected to reduce the radionuclide ingestion dose after a nuclear accident must be made appropriate by considering the accident situation, such as the soil deposition density of the radionuclide and the deposition date in relation to farming cycles.

• 대한방사선기술학회지:방사선기술과학
• /
• 제45권2호
• /
• pp.127-134
• /
• 2022

In order to overcome the image quality limitations of the conventional C-arm, a flat panel detector (FPD) is used to enhance spatial resolution, detective quantum efficiency, frame rate, and dynamic range. Three-dimensional (3D) visualized information can be obtained from C-arm computed tomography (CT) equipped with an FPD, which can reduce patient discomfort and provide various medical information to health care providers by conducting procedures in the interventional procedure room without moving the patient to the CT scan room. Unlike a conventional C-arm device, a C-arm CT requires different basic safety and essential performance evaluation criteria; therefore, in this study, basic safety and essential performance evaluation criteria to protect patients, medical staff, and radiologists were derived based on International Electrotechnical Commission (IEC) standards, the Ministry of Food and Drug Safety (MFDS) standards in Korea, and the rules on the installation and operation of special medical equipment in Korea. As a result of the study, six basic safety evaluation criteria related to electrical and mechanical radiation safety (leakage current, collision protection, emergency stopping device, overheating, recovery management, and ingress of water or particulate matter into medical electrical (ME) equipment and ME systems: footswitches) and 14 essential performance evaluation criteria (accuracy of tube voltage, accuracy of tube current, accuracy of loading time, accuracy of current time product, reproducibility of radiation output, linearity and consistency in radiography, half layer value in X-ray equipment, focal size and collimator, relationship between X-ray field and image reception area, consistency of light irradiation versus X-ray irradiation, performance of the mechanical device, focal spot to skin distance accuracy, image quality evaluation, and technical characteristic of cone-beam computed tomography) were selected for a total of 20 criteria.

• Nuclear Engineering and Technology
• /
• 제53권11호
• /
• pp.3505-3516
• /
• 2021

During nuclear facility decommissioning, workers are continuously exposed to high-level radiation. Hence, adequate path planning is critical to protect workers from unnecessary radiation exposure. This work discusses recent development in radioactive path planning and the algorithms recommended for the task. Specifically, we review the conventional methods for nuclear decommissioning path planning, analyze the techniques utilized in developing algorithms, and enumerate the decision factors that should be considered to optimize path planning algorithms. As a major contribution, we present the quantitative performance comparison of different algorithms utilized in solving path planning problems in nuclear decommissioning and highlight their merits and drawbacks. Also, we discuss techniques and critical consideration necessary for efficient application of robots and robotic path planning algorithms in nuclear facility decommissioning. Moreover, we analyze the influence of obstacles and the environmental/radioactive source dynamics on algorithms' efficiency. Finally, we recommend future research focus and highlight critical improvements required for the existing approaches towards a safer and cost-effective nuclear-decommissioning project.

• Nuclear Engineering and Technology
• /
• 제56권7호
• /
• pp.2437-2443
• /
• 2024

This work synthesized four glass samples with a fixed ratio of PbO to Na₂O and a variable ratio of BaO to B₂O₃. The linear attenuation coefficient (LAC) (μ, cm^-1) and additional attenuator parameters were determined experimentally using a semiconductor detector and different gamma sources. The comparison was carried out between the experimental and the XCOM calculated results, with good agreement emerging between the two results. The impacts of the BaO substituting for the B₂O₃ on fabricated PNBB glasses' radiation shielding properties were discussed. By increasing the BaO substitution concentration between 10 and 25 mol.%, the LAC μ values (cm^-1) increased by 76.60 %, 13.81 %, 12.56 %, and 12.52 % for the respective γ-ray energies of 0.059, 0.662, 1.173, and 1.332 MeV. The μ value reduction with raised gamma energy values increased the values of the calculated half-value thickness (Δ_0.5) as a result of the μ and Δ_0.5 values' reverse proportionality. Other shielding parameters such as the lead equivalent thickness (Δ_eq) and radiation protection efficiency were also determined for the present PNBB glass samples.

• 한국방사선학회논문지
• /
• 제13권2호
• /
• pp.271-281
• /
• 2019

본 연구는 다양한 종류의 차폐체가 가진 차폐 효율을 확인하고, 인체모형 팬텀을 활용해 깊이에 따른 장기별 선량을 측정한 것이다. 개인방사선량측정기를 이용한 차폐체 차폐효율 측정 결과 다양한 차폐체 중 나노텅스텐으로 구성된 1.1 mm RNS-TX가 가장 높은 차폐 효율을 보였고, 0.2 mm 납 차폐체가 가장 낮은 차폐 효율을 보였다. $^{99m}Tc$ 30 mCi를 120분 동안 팬텀에 노출시킨 뒤 장기가 받은 선량 측정 결과. 방사선 방호복을 착용하지 않은 경우, 0.25 mm Pb, 0.5 mm Pb 방호복을 착용한 경우, 장기의 평균 선량은 각각 20.53 mSv, 8.75 mSv, 6.03 mSv로 나타났다. $^{131}I$ 2 mCi를 120분 동안 팬텀에 노출시킨 뒤 장기가 받은 선량 측정 결과, 방사선 방호복을 착용하지 않은 경우, 0.25 mm Pb, 0.5 mm Pb 방호복을 착용한 경우, 장기의 평균 선량은 각각 7.71 mSv, 4.88 mSv, 2.79 mSv로 나타났다. $^{18}F$ 5 mCi를 120분 동안 팬텀에 노출 시킨 뒤 장기가 받은 선량 측정 결과. 방사선 방호복을 착용하지 않은 경우, 0.25 mm Pb, 0.5 mm Pb 방호복을 착용한 경우, 장기의 평균 선량은 각각 16.39 mSv, 15.84 mSv, 12.52 mSv로 나타났다. 핵의학 작업종사자의 피폭선량이 한도를 넘지 않는다고 하더라도, 병원 내 타 직군 종사자와 비교 했을 때, 상대적으로 높은 피폭선량을 보이므로 가볍고 차폐효율이 좋은 차폐물질로 개발된 방사선방호복 착용, 순환 업무, 업무 분담, 오토분주기와 같은 대체 장비 도입 등을 통해 핵의학 작업종사자의 선량을 줄이고, 관리할 수 있어야 한다.

• Journal of Radiation Protection and Research
• /
• 제24권2호
• /
• pp.73-86
• /
• 1999

현재 경수로형 원자력발전소의 일차계통 냉각수 정화를 위해 사용되는 이온교환방법은 제염효과가 우수하고 공정이 단순하며 조작이 간편하기 때문에 광범위하게 활용되고 있으나 비금속성분도 함께 제거하여 수지의 수명이 단축되고 폐이온교환수지가 발생되는 단점이 있다. 본 연구에서는 일차계통 냉각수 정화를 위해 사용되는 이온교환수지의 대체공정으로서 전기투석과 이온교환이 결합된 전기탈이온법의 사용가능성을 조사하기 위해 모의 용액을 이용하여 다양한 실험조건하에서 수행하였다. 실험결과 유입유량이 증가할수록 제거율은 증가하고 전력소모는 감소하였다. 금속성분 제거율에서 제염계수 1000으로 일정한 경향을 나타내었으며 전력소모 면에서는 TDS 3 ppm이하를 기준으로 유입유량이 $2.0{\ell}/min$일 때 $40.3mWh/{\ell}$ 이었다. 유입유속이 동일한 조건에서는 희석실에 채운 이온 교환수지의 함량이 증가할수록 금속성분 제거율과 전력소모에서 효과적인 것으로 평가되었다. 이온 교환수지를 채운 전기탈이온 공정은 이온교환수지 자체에 의한 수리적 저항과 현탁질에 의한 수지의 오염으로 인해 운전이 계속될수록 유량이 감소하게 된다. 이러한 단점을 극복하기 위해 이온교환수지 대신 이온전도성 스페이서를 설치하여 실험한 결과 유입유량 문제는 해결할 수 있었으나 전력소모와 금속성분 제거율 및 전류효율 면에서 비효율적인 것으로 평가되었다. 전기탈이온 공정의 연속운전에서도 금속성분 제거율에서 제염계수가 1000으로 안정적인 수준을 유지하였다.

• Nuclear Engineering and Technology
• /
• 제55권9호
• /
• pp.3150-3163
• /
• 2023

To improve the performance of blanket: maximizing the tritium breeding rate (TBR) for tritium self-sufficiency, and minimizing the Dose of backplate for radiation protection, most previous studies are based on manual corrections to adjust the blanket structure to achieve optimization design, but it is difficult to find an optimal structure and tends to be trapped by local optimizations as it involves multiphysics field design, which is also inefficient and time-consuming process. The artificial intelligence (AI) maybe is a potential method for the optimization design of the blanket. So, this paper aims to develop an intelligent optimization method based on an improved multi-objective NSGA-III algorithm and an adaptive BP neural network to solve these problems mentioned above. This method has been applied on optimizing the radial arrangement of a conceptual design of CFETR HCSB blanket. Finally, a series of optimal radial arrangements are obtained under the constraints that the temperature of each component of the blanket does not exceed the limit and the radial length remains unchanged, the efficiency of the blanket optimization design is significantly improved. This study will provide a clue and inspiration for the application of artificial intelligence technology in the optimization design of blanket.