• Journal of Radiation Protection and Research
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• 제45권2호
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• pp.69-75
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• 2020

Background: Dose conversion coefficients (DCCs) have been commonly used to estimate radiation-dose absorption by human organs based on physical measurements of fluence or kerma. The International Commission on Radiological Protection (ICRP) has reported a library of DCCs, but few studies have been conducted on their applicability to non-Caucasian populations. In the present study, we collected a total of 8 Korean pediatric and adult voxel phantoms to calculate the organ DCCs for idealized external photon-irradiation geometries. Materials and Methods: We adopted one pediatric female phantom (ETRI Child), two adult female phantoms (KORWOMAN and HDRK Female), and five adult male phantoms (KORMAN, ETRI Man, KTMAN1, KTMAN2, and HDRK Man). A general-purpose Monte Carlo radiation transport code, MCNPX2.7 (Monte Carlo N-Particle Transport extended version 2.7), was employed to calculate the DCCs for 13 major radiosensitive organs in six irradiation geometries (anteroposterior, posteroanterior, right lateral, left lateral, rotational, and isotropic) and 33 photon energy bins (0.01-20 MeV). Results and Discussion: The DCCs for major radiosensitive organs (e.g., lungs and colon) in anteroposterior geometry agreed reasonably well across the 8 Korean phantoms, whereas those for deep-seated organs (e.g., gonads) varied significantly. The DCCs of the child phantom were greater than those of the adult phantoms. A comparison with the ICRP Publication 116 data showed reasonable agreements with the Korean phantom-based data. The variations in organ DCCs were well explained using the distribution of organ depths from the phantom surface. Conclusion: A library of dose conversion coefficients for major radiosensitive organs in a series of pediatric and adult Korean voxel phantoms was established and compared with the reference data from the ICRP. This comparison showed that our Korean phantom-based data agrees reasonably with the ICRP reference data.

• 한국응용과학기술학회지
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• 제15권4호
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• pp.11-20
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• 1998

The propagation of light radiation in a turbid medium is an important problem that confronts dosimetry of therapeutic laser delivery and the development of diagnostic spectroscopy. Scattered light is measured as a function of the position(distance r, depth z) between the axis of the incident beam and the detection spot. Turbid sample yields a very forward-directed scattering pattern at short range of position from source to detector, whereas the thicker samples greatly attenuated the on-axis intensity at long range of position. The portions of scattered light reflected from or transmitted throughphantom depend upon internal reflectance and absorption properties of the phantom. Monte Carlo simulation method for modelling light transport in tissue is applied. It uses the photon is moved a distance where it may be scattered, absorbed, propagated, internally reflected, or transmitted out of tissue. The photon is repeatedly moved until it either escape from or is absorbed by the phantom. In order to obtain an optimum therapeutic ratio in phantom material, optimum control the light energy fluence rate is essential. This study is to discuss the physical mechanisms determining the actual light dose in phantom. Permitting a qualitative understanding of the measurements. It may also aid in designing the best model for laser medicine and application of medical engineering.

• Nuclear Engineering and Technology
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• 제47권3호
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• pp.253-259
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• 2015

The fast neutron reactor BOR-60 is one of the key experimental facilities worldwide to perform large-scale tests of fuel, absorbing, and structural materials for advanced reactors. The BOR-60 reactor was put into operation in December 1969, and by the end of 2014 it had been operating on power for ~265,000 hours. BOR-60 still demonstrates potential capabilities to extend the lifetime of sodium-cooled fast reactors. The BOR-60 lifetime should have expired at the end of 2014. Over the past few years, a great scope of work has been performed to justify the possibility of extending its lifetime. The work included inspection of the equipment conditions, calculations and experimental research on operating parameters and the conditions of nonremovable components, investigation of the structural material samples after their long-term operation under irradiation, etc. Based on the results of the work performed, the residual lifetime was evaluated and the reactor operator made a decision to extend the lifetime period of the BOR-60 reactor. After considering both a set of documents about the reactor conditions and the positive decision of independent experts, the Regulatory Authority of the Russian Federation extended the BOR-60 operating license up to 2020.

• Nuclear Engineering and Technology
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• 제48권5호
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• pp.1219-1229
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• 2016

The present paper reports on a trial to shed further light on the characterization, applications, and operation of radar speed guns or Gunn diodes on different radiation environments of neutron or g fields. To this end, theoretical and experimental investigations of microwave oscillating system for outer-space applications were carried out. Radiation effects on the transient parameters and electrical properties of the proposed devices have been studied in detail with the application of computer programming. Also, the oscillation parameters, power characteristics, and bias current were plotted under the influence of different ${\gamma}$ and neutron irradiation levels. Finally, shelf or oven annealing processes were shown to be satisfactory techniques to recover the initial characteristics of the irradiated devices.

• Nuclear Engineering and Technology
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• 제46권2호
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• pp.273-280
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• 2014

The spectrum weighted responses of various detectors were calculated to provide guidance on the proper selection and use of survey instruments on the basis of their energy response characteristics on the neutron fields. To yield the spectrum weighted response, the detector response functions of 17 neutron-measuring devices were numerically folded with each of the produced calibration neutron spectra through the in-house developed software 'K-SWR'. The detectors' response functions were taken from the IAEA Technical Reports Series No. 403 (TRS-403). The reference neutron fields of 21 kinds with 2 spectra groups with different proportions of thermal and fast neutrons have been produced using neutrons from the $^{241}Am$-Be sources held in a graphite pile, a bare $^{241}Am$-Be source, and a DT neutron generator. Fluence-average energy ($E_{ave}$) varied from 3.8 MeV to 16.9 MeV, and the ambient-dose-equivalent rate [$H^*(10)/h$] varied from 0.99 to 16.5 mSv/h.

• 한국유체기계학회 논문집
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• 제18권2호
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• pp.54-59
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• 2015

The performance of UV reactor which is used in water treatment is strongly affected by UV fluence rate and water flow in the UV reactor. Therefore, CFD tools are widely used in designing process of UV reactors. This paper describes the development of a computational fluid dynamics (CFD) methodology that can be used to calculate the performance of open channel type UV reactor used in wastewater treatment plant. All computations were performed using commercial CFD code, CFX, by considering three dimensional, steady, incompressible flow. The Eulerian-Eulerian multi-phase method were used to capture the water-air interface. The MSSS model, provided by UVCalc3D, was used to calculate the UV intensity field. The numerical predictions and calculated UV Dose were compared with experimental dataset to validate the CFD methodology. The reactor performance based on MS2 log reduction was well matched with measurements within 6%.

• Corrosion Science and Technology
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• 제20권4호
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• pp.210-229
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• 2021

To safely operate domestic nuclear power plants approaching the end of their design life, the material degradation management strategy of the components is important. Among studies conducted to improve the soundness of nuclear reactor components, research methods for understanding the degradation of reactor internals and preparing management strategies were surveyed. Since the IGSCC (Intergranular Stress Corrosion Cracking) initiation and propagation process is associated with metal dissolution at the crack tip, crack initiation sensitivity was decreased in the hydrogenated water with decreased crack sensitivity but occurrence of small surface cracks increased. A stress of 50 to 55% of the yield strength of the irradiated materials was required to cause IASCC (Irradiation Assisted Stress Corrosion Cracking) failure at the end of the reactor operating life. In the threshold-stress analysis, IASCC cracks were not expected to occur until the end of life at a stress of less than 62% of the investigated yield strength, and the IASCC critical dose was determined to be 4 dpa (Displacement Per Atom). The stainless steel surface oxide was composed of an internal Cr-rich spinel oxide and an external Fe and Ni-rich oxide, regardless of the dose and applied strain level.

• 한국의학물리학회지:의학물리
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• 제19권1호
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• pp.80-88
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• 2008

최근의 방사선 치료선량 계획시스템은 대체로 커널빔을 컨볼루션하여 조직선량을 구하고 있다. 본 연구에서는 광자선 빔에 따른 심부선량과 임의의 깊이에서 프로파일 선량을 구하기 위하여 반복적 수치해석을 통해 투과 필터에 의한 감쇠선량으로부터 에너지 스펙트럼을 구성하였다. 실험은 15 MV X선(Oncor, Siemens사)과 이온선량계 0.125 cc (PTW T31010)을 이용하여 납필터를 투과한 선량을 측정하여 이루어졌다. 15 MV X선의 에너지스펙트럼은 0.25 MeV 간격으로 납필터 0.51 cm에서 8.04 cm의 감쇠선량으로 실측치와 비교하여 구하였다. 실험 연산에서 15 MV X선의 최대유량은 3.75 MeV에서 나타났으며, 평균에너지는 4.639 MeV를 보였으며, 투과선량은 평균 0.6%의 오차인 반면에 최대오차는 납두께 5 cm에서 2.5%를 보였다. 조직선량은 에너지에 크게 의존하므로, 평탄형 필터의 중심과 Tangent 0.075와 0.125인 가장자리의 에너지를 구하였으며, 각각 4.211 MeV와 3.906 MeV로 나타났다. 심부선량과 프로파일 선량은 상업화로 공급되고 있는 선량계획시스템에 중심 선속과 가장자리의 각 에너지스펙트럼을 적용하여 구하여 실측선량률과 비교하였다. 생성된 심부선량 곡선은 조사면 $6{\times}6cm^2$에서 $30{\times}30cm^2$까지 실측치와 비교한 결과 1% 이내의 거의 일치하는 값을 얻었으며, 프로파일 곡선은 $10{\times}10cm^2$에서 1% 이내의 오차를 보였으나, $30{\times}30cm^2$와 같이 큰 조사면의 얕은 깊이에서는 2%의 오차를 보였다. 따라서 투과선량을 연산으로 구한 에너지 스펙트럼이 조직선량을 평가하는 데 상당히 적은 오차범위 내에서 정량적이고 정성적으로 얻을 수 있음을 알 수 있다.

• 한국방사선학회논문지
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• 제10권5호
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• pp.327-335
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• 2016

본 연구는 IEC에서 제시하는 영상품질을 평가하는 조건으로는 임상적인 환경에서 디지털 방사선영상시스템(Digital Radiography System)에서의 검출기에 대한 영상품질평가를 시행하기에는 환경적인 제한점이 있기에 IEC에서 제시하는 조건과 임상검사조건을 조합한 각각의 선질에 대하여 영상품질평가를 시행한 연구입니다. 첫째, 네 가지 선질을 사용하여 MTF, NPS 영상품질평가를 하였으며, MCNPX 시뮬레이션을 이용하여 선질들에 대한 스펙트럼을 분석하여 입자 플루언스를 산정한 후 최종적으로 DQE 영상품질평가를 하였다. 둘째, 네 가지 선질들의 MCNPX 시뮬레이션을 이용하여 방사선속 밀도와 에너지, 물질의 질량에너지 흡수계수를 이용하여 전자 1 개당 공기, 물, 근육, 뼈에 대한 흡수선량률을 평가하였다. 영상품질을 평가한 결과, 네 가지 선질들의 MTF는 1.13 ~ 2.91 lp/mm 공간주파수를 나타내어 일반 X선 촬영의 진단 주파수 영역인 1.0 ~ 3.0 lp/mm를 만족하였다. NPS는 부가필터를 사용하면, 공간 주파수가 0.5 lp/mm 기준으로 NPS가 증가하다가 이후, 감소하는 경향성을 나타내었다. 부가필터 미사용하면, 공간주파수가 0.5 lp/mm 기준으로 NPS가 감소하다가 이후, 일정한 NPS 결과 값을 나타내었다. DQE는 70 kVp / unuesd added filter(21mm Al) / SID 150 cm에서 공간주파수 1.5 lp/mm 기준으로 일정한 값을 나타내다가 이후, 감소하는 경향성을 나타내었다. 나머지 선질들은 공간주파수가 증가함에 따라 감소하는 경향성을 나타내었다. 흡수선량 평가결과는 공기 < 물 < 근육 < 뼈 순서로 흡수선량이 증가함을 나타내었다. 본 연구결과를 바탕으로 다양한 임상환경에서 디지털 방사선영상시스템의 영상품질평가 방법을 제시할 수 있는 기초자료로 제공하고자 한다.

• 한국가스학회지
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• 제17권4호
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• pp.18-25
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• 2013

맨홀 또는 환기가 부족한 공간에서 작업 중 유해 가스나 산소결핍에 의한 질식 또는 급성중독에 의한 건강장해나 사망사고가 빈번히 발생되고 있다. 따라서 유해가스에 의한 급성중독이나 산소결핍에 의한 유해농도 규명과 재해발생시 원인규명 자료로 활용하고자 산소결핍과 유해가스 노출에 따른 사망농도 시험하고자 하였다. 특히 산소결핍 상황에서 유해가스의 영향에 대해서도 시험하였으며, 국내외에서 발생된 관련 각종 사고 사례 조사를 통하여 동종재해를 예방하고자 하였다. 자료를 조사한 결과 산소결핍 또는 유해가스 노출에 의한 사망 재해는 하절기(6-8월)에 전체의 50%가 발생하고, 업종은 건설업 40%, 장소는 맨홀 50%, 원인은 산소결핍이 가장 많았으며(40%), 기타 가스($H_2S$, CO, $N_2$, Ar 등) 및 환경적 요인(내부 온도, 바닥 물 익사)도 크게 작용하였다. 동물실험 결과 산소결핍에 의한 치사 산소농도는 5%수준이었으며 Dose-Response의 통계처리결과 과반수치사농도 $LC_{50}$(rat, 4hr)는 5.5%로 산출되었다. 또한 산소결핍(6%수준) 상황에서 다른 유해물질이 혼합 될 경우 미치는 치사농도 시험 결과 $H_2S$ 20 ppm에서 40%치사, CO는 600 ppm에서 20%치사, 톨루엔은 1,000 ppm에서도 사망 예가 증가하지 않았다. 즉, $H_2S$, CO 등은 치사농도에 민감하게 반응하는 유해물질로의 상승작용을 했다.