• Nuclear Engineering and Technology
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• 제48권3호
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• pp.785-794
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• 2016

The Argonne National Laboratory of the United States and the Kharkov Institute of Physics and Technology of the Ukraine have been collaborating on the design, development and construction of a neutron source facility at Kharkov Institute of Physics and Technology utilizing an electron-accelerator-driven subcritical assembly. The electron beam power is 100 kW using 100-MeV electrons. The facility was designed to perform basic and applied nuclear research, produce medical isotopes, and train nuclear specialists. The biological shield of the accelerator building was designed to reduce the biological dose to less than 5.0e-03 mSv/h during operation. The main source of the biological dose for the accelerator building is the photons and neutrons generated from different interactions of leaked electrons from the electron gun and the accelerator sections with the surrounding components and materials. The Monte Carlo N-particle extended code (MCNPX) was used for the shielding calculations because of its capability to perform electron-, photon-, and neutron-coupled transport simulations. The photon dose was tallied using the MCNPX calculation, starting with the leaked electrons. However, it is difficult to accurately tally the neutron dose directly from the leaked electrons. The neutron yield per electron from the interactions with the surrounding components is very small, ~0.01 neutron for 100-MeV electron and even smaller for lower-energy electrons. This causes difficulties for the Monte Carlo analyses and consumes tremendous computation resources for tallying the neutron dose outside the shield boundary with an acceptable accuracy. To avoid these difficulties, the SOURCE and TALLYX user subroutines of MCNPX were utilized for this study. The generated neutrons were banked, together with all related parameters, for a subsequent MCNPX calculation to obtain the neutron dose. The weight windows variance reduction technique was also utilized for both neutron and photon dose calculations. Two shielding materials, heavy concrete and ordinary concrete, were considered for the shield design. The main goal is to maintain the total dose outside the shield boundary less than 5.0e-03 mSv/h during operation. The shield configuration and parameters of the accelerator building were determined and are presented in this paper.

• 한국의학물리학회지:의학물리
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• 제27권4호
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• pp.272-276
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• 2016

To investigate the optimum x-ray tube design for the dental radiology, factors affecting x-ray beam characteristics such as tungsten target thickness and anode angle were evaluated. Another goal of the study was to addresses the anode heel effect and off-axis spectra for different target angles. MCNPX has been utilized to simulate the diagnostic x-ray tube with the aim of predicting optimum target angle and angular distribution of x-ray intensity around the x-ray target. For simulation of x-ray spectra, MCNPX was run in photon and electron using default values for PHYS:P and PHYS:E cards to enable full electron and photon transport. The x-ray tube consists of an evacuated 1 mm alumina envelope containing a tungsten anode embedded in a copper part. The envelope is encased in lead shield with an opening window. MCNPX simulations were run for x-ray tube potentials of 70 kV. A monoenergetic electron source at the distance of 2 cm from the anode surface was considered. The electron beam diameter was 0.3 mm striking on the focal spot. In this work, the optimum thickness of tungsten target was $3{\mu}m$ for the 70 kV electron potential. To determine the angle with the highest photon intensity per initial electron striking on the target, the x-ray intensity per initial electron was calculated for different tungsten target angles. The optimum anode angle based only on x-ray beam flatness was 35 degree. It should be mentioned that there is a considerable trade-off between anode angle which determines the focal spot size and geometric penumbra. The optimized thickness of a target material was calculated to maximize the x-ray intensity produced from a tungsten target materials for a 70 keV electron energy. Our results also showed that the anode angle has an influencing effect on heel effect and beam intensity across the beam.

• 한국정보통신학회:학술대회논문집
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• 한국정보통신학회 2014년도 춘계학술대회
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• pp.816-818
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• 2014

갑상선암 진단 방사성의약품인 $^{123}I$ 생산을 목적으로 한 가스타겟챔버를 개발하고 MCNPX를 이용해 30MeV 빔에너지 가 가스타겟챔버에 어떻게 들어가는지와 들어갔을 경우의 $^{124}Xe$와 핵반응은 어떻게 발생하는지를 모델링하였다. 빔에너지 가 확산되어 가스타겟챔버 내경에 맞아 에너지 손실이 생긴다. 그것은 즉 손실된 에너지가 열로 바뀜으로 타겟챔버가 변형이 일어나기 않게 냉각수를 이용한다. 쿨링시스템도 타겟챔버를 효율적으로 냉각하기위해 냉각수라인을 나선형으로 설계하였다. KIRAMS에서 보유하고 있는 사이크로트론 C30을 이용하여 30MeV 에너지에 100A 빔을 조사해 $^{124}Xe(p,2n)$, $^{124}Xe(p,n)$, $^{124}Xe(p,pn)$ 각각의 핵반응이 일어나는걸 알 수 있었고 생산량을 예측 할 수 있었다.

• 한국방사선학회논문지
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• 제14권5호
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• pp.523-528
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• 2020

반려견의 사망원인 1위인 암 중 암컷에게서 가장 높은 발생률을 보이는 유방암을 대상으로 근접방사선치료 수행 시 모의모사를 이용한 흡수선량 측정을 바탕으로 적용성을 평가하고자 하였다. 모의모사를 위해 MCNPX 프로그램을 이용하였으며, 흡수선량 측정을 위해 소형견 크기의 수학적 팬텀을 제작 하였다. 흡수선량 측정결과 종양의 경우 ¹⁹²Ir에서 1.02E-12 Gy/#으로 흡수선량이 가장 높은 것으로 나타났으며, 내·외부 흡수선량에서도 동일한 경향성으로 나타났다. 따라서 반려견 유방암의 근접방사선치료 시 견종과 피폭을 고려한 적절한 선원의 선택이 고려되어야 될 것이다.

• Nuclear Engineering and Technology
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• 제50권1호
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• pp.25-34
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• 2018

The CINDER code has about 60 years of development history, and is thus one of the world's best transmutation computing codes to date. Unfortunately, it is complex and cumbersome to use. Preparing auxiliary input files for activation computation from MCNPX output and executing them using Perl script (activation script) is the first difficulty, and separation of gamma source computing script (gamma script), which analyzes the spectra files produced by CINDER code and creates source definition format for MCNPX code, is the second difficulty. In addition, for highly nonlinear problems, multiple human interventions may increase the possibility of errors. Postprocessing such as making plots with large text outputs is also time consuming. One way to improve these limitations is to make a graphical user interface wrapper that includes all codes, such as MCNPX and CINDER, and all scripts with a visual C#.NET tool. The graphical user interface merges all the codes and provides easy postprocessing of graphics data and Microsoft office tools, such as Excel sheets, which make the CINDER code easy to use. This study describes the VCINDER code (with visual C#.NET) and gives a typical application example.

• 한국방사선학회논문지
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• 제13권2호
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• pp.241-246
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• 2019

4차 산업혁명의 기술 중 3D 프린팅 기술의 소재에 따른 선량평가를 통해 볼루스 적용 가능성을 평가하였다. 선량의 평가는 몬테카를로 방식의 MCNPX프로그램을 이용하였으며, 3D 프린트 물성은 ABS, PC, PLA 세 가지로 하였다. 그리하여 볼루스 10 mm와 동일한 효과를 보이는 두께를 산정한 결과 6 MeV 전자선의 경우 ABS 10 mm, PC 9 mm, PLA 9 mm로 나타났다. 6 MV X-선의 경우 ABS 11 mm, PC 10 mm, PLA 9 mm로 나타났다. 본 실험을 통해 3D 프린터 소재로 제작하는 조직등가물질이 볼루스를 대체할 수 있음을 확인할 수 있었다.

• 한국방사선학회논문지
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• 제13권1호
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• pp.45-53
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• 2019

본 연구는 의료용 선형가속기 시설을 차폐하는 콘크리트에 대한 중성자 방사화 연구로써, 일반 콘크리트와 저 방사화 콘크리트를 비교 분석하였다. 실험 방법은 MCNPX (Ver. 2.5.0)와 FISPACT-2010를 사용하여 모의실험을 진행하여, 광자선과 중성자선에 대한 차폐능을 산정하고 중성자 방사화 평가를 진행하였다. 그 결과 차폐능은 일반 콘크리트에서 20~50 cm 효율적이였으며, 방사화 평가의 경우 저 방사화 콘크리트에서 방사능이 낮게 계산되었으나, 모두 자체처분허용 농도를 초과하지 않는 수준으로 산정되었다. 이를 종합적으로 분석한 결과 일반 콘크리트를 사용하는 것이 효율적인 것으로 판단된다.

• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2975-2981
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• 2020

Radiation damage is one of the aging important causes in nuclear reactors. Radiation damage causes changes in material properties. In this study, this effect has been evaluated and analyzed on the clad of the Tehran research reactor (TRR). A grade 6061 aluminum is used as a clad in the TRR. The MCNPX code is used to designate the most sensitive location of the reactor and calculate neutron flux distribution. Then, a software using FORTRAN language programming is developed to process the particle track (PTRAC) output file of the MCNPX code. The SRIM code is used here to calculate the rate of displacement per atom. Moreover, the SPECOMP and SPECTER codes are also applied to estimate the displacement rate and compared with the results attained using the SRIM code. The rate of displacement per atom by the SPECTER and SRIM codes have been obtained 2.54 × 10^-7 dpa/s and 2.44 × 10^-7 dpa/s (QD method), respectively. Also, the mechanical properties have been evaluated using the RCC-MRx code and have been compared with experimental results. Finally, the change in the matter specification has been analyzed as a function of time.

• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2852-2859
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• 2020

This paper deals with the simulation-based design optimization and experimental validation of the characteristics of an in-core silver Self-Powered Neutron Detector (SPND). Optimized dimensions of the SPND are determined by combining Monte Carlo simulations and analytical methods. As a first step, the Monte Carlo transport code MCNPX is used to follow the trajectory and fate of the neutrons emitted from an external source. This simulation is able to seamlessly integrate various phenomena, including neutron slowing-down and shielding effects. Then, the expected number of beta particles and their energy spectrum following a neutron capture reaction in the silver emitter are fetched from the TENDEL database using the JANIS software interface and integrated with the data from the first step to yield the origin and spectrum of the source electrons. Eventually, the MCNPX transport code is used for the Monte Carlo calculation of the ballistic current of beta particles in the various regions of the SPND. Then, the output current and the maximum insulator thickness to avoid breakdown are determined. The optimum design of the SPND is then manufactured and experimental tests are conducted. The calculated design parameters of this detector have been found in good agreement with the obtained experimental results.

• Journal of Radiation Protection and Research
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• 제36권2호
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• pp.59-63
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• 2011

가속기 기반 중성자 표준장은 검출기 및 도시메터 교정, 핵자료 생산, 동위원소 생산등 에 필수적으로 필요한 기반 장비이다. 가속기 기반 중성자 표준장 실험실을 설계하는데 있어서 원하는 에너지의 직접적인 중성자 이외에 산란되어서 입사하는 산란 중성자를 줄이는 것은 매우 중요하다. 따라서 그러한 조건을 얻어내기 위하여 다양한 조건을 가정하여 MCNPX 모사계산을 수행하였다. 우선은 기존의 실험실 조건에서 양성자 운동방향인 0도 방향에 있는 중성자 Flux 측정용 공기로 이루어진 가상의 Chamber에 직접 입사하는 중성자 flux와 벽이나 바닥에 충돌을 한 후에 입사하는 간접적인 산란 중성자 flux를 각각 계산하였다. 그 결과 충돌 한 후에 0도 방향의 Chamber에 입사하는 산란 중성자 flux 중에 바닥에 충돌을 한 후 0도 방향의 Chamber로 입사하는 산란 중성자 flux가 가장 많다는 것을 알 수 있었다. 따라서 바닥의 콘크리트만을 없앴을 때와 콘크리트를 제거하고 땅을 1m 정도 파내려갔을 때를 가정하여 재계산을 하였고 그 결과 콘크리트를 없애고 땅을 1m 정도 파면 바닥에 충돌하고 Chamber로 들어오는 산란 중성자 flux가 다른 곳에 충돌하고 들어오는 것보다 낮아지는 정도까지 줄어드는 것을 알 수 있었다.