• 제목/요약/키워드: GEANT

검색결과 168건 처리시간 0.031초

GEANT4, SPENVIS 를 이용한 STEIN 검출기의 배경계수 예측

  • 전종호;박성하;김용호;선종호;진호;이동훈
    • 천문학회보
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    • 제37권2호
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    • pp.230.2-230.2
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    • 2012
  • 경희대학교에서 제작중인 초소형 위성 TRIO-CINEMA (TRiplet Ionosphere Observatory-Cubesat for Ion, Neutral, Electron and MAgnetic fields)에 탑재될 입자검출기 STEIN (SupraThermal Electron, Ion, Neutral)은 정전 편향기를 이용하여 4~300keV의 대전입자 혹은 중성입자들을 분리하여 검출하도록 이루어져있다. CINEMA 운용 궤도에서는 STEIN 정전 편향기를 통하지 않고 검출기 내부로 들어오는 입자들로부터 생기는 배경계수가 포함되어 검출될 것으로 예상되므로 STEIN 검출기의 결과값의 신뢰성을 높이기 위해 배경계수값을 예측할 필요성이 있다. 본 연구에서는 SPENVIS (The Space Environment Information System)를 통해 CINEMA 운용 궤도에 존재하는 입자들의 유량을 계산하였고 GEANT4 (GEometry ANd Tracking)를 통해 CINEMA 운용 궤도상의 STEIN의 외부 환경을 모사하여 배경계수값을 예측하였다. 향후 STEIN의 측정값에 배경계수값을 차감한다면 측정값의 신뢰성이 높아질 것으로 기대된다.

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Lost gamma source detection algorithm based on convolutional neural network

  • Fathi, Atefeh;Masoudi, S. Farhad
    • Nuclear Engineering and Technology
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    • 제53권11호
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    • pp.3764-3771
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    • 2021
  • Based on the convolutional neural network (CNN), a novel technique is investigated for lost gamma source detection in a room. The CNN is trained with the result of a GEANT4 simulation containing a gamma source inside a meshed room. The dataset for the training process is the deposited energy in the meshes of different n-step paths. The neural network is optimized with parameters such as the number of input data and path length. Based on the proposed method, the place of the gamma source can be recognized with reasonable accuracy without human intervention. The results show that only by 5 measurements of the energy deposited in a 5-step path, (5 sequential points 50 cm apart within 1600 meshes), the gamma source location can be estimated with 94% accuracy. Also, the method is tested for the room geometry containing the interior walls. The results show 90% accuracy with the energy deposition measurement in the meshes of a 5-step path.

Design and performance prediction of large-area hybrid gamma imaging system (LAHGIS) for localization of low-level radioactive material

  • Lee, Hyun Su;Kim, Jae Hyeon;Lee, Junyoung;Kim, Chan Hyeong
    • Nuclear Engineering and Technology
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    • 제53권4호
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    • pp.1259-1265
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    • 2021
  • In the present study, a large-area hybrid gamma imaging system was designed by adopting coded aperture imaging on the basis of a large-area Compton camera to achieve high imaging performance throughout a broad energy range (100-2000 keV). The system consisting of a tungsten coded aperture mask and monolithic NaI(Tl) scintillation detectors was designed through a series of Geant4 Monte Carlo radiation transport simulations, in consideration of both imaging sensitivity and imaging resolution. Then, the performance of the system was predicted by Geant4 Monte Carlo simulations for point sources under various conditions. Our simulation results show that the system provides very high imaging sensitivity (i.e., low values for minimum detectable activity, MDA), thus allowing for imaging of low-activity sources at distances impossible with coded aperture imaging or Compton imaging alone. In addition, the imaging resolution of the system was found to be high (i.e., around 6°) over the broad energy range of 59.5-1330 keV.

Validation of electromagnetic physics models and electron range in Geant4 Brachytherapy application

  • A. Albqoor ;E. Ababneh ;S. Okoor;I. Zahran
    • Nuclear Engineering and Technology
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    • 제55권1호
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    • pp.229-237
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    • 2023
  • The mechanics underlying photon and electron interactions was validated using our developed Brachytherapy computer code for high Dose Rate (HDR). By comparing the photon cross-section utilizing multiple physics libraries in the developed code, the results were benchmarked against experimental and theoretical findings. Klein-Nishina and experimental cross-section results were in good agreement with the Livermore library results. For two therapeutically relevant materials, the first scattered electron range was measured within 1 mm and 2 mm, which has significant implications for the interpretation of the kernel dose spikes observed in previous research.

Modeling of Space Radiation Exposure Estimation Program for Pilots, Crew and Passengers on Commercial Flights

  • Hwang, Junga;Dokgo, Kyunghwan;Choi, Enjin;Park, Jong-Sun;Kim, Kyung-Chan;Kim, Hang-Pyo
    • Journal of Astronomy and Space Sciences
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    • 제31권1호
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    • pp.25-31
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    • 2014
  • There has been a rapid increase of the concern on the space radiation effect on pilots, crew and passengers at the commercial aircraft altitude (~ 10 km) recently. It is because domestic airline companies, Korean Air and Asiana Airlines have just begun operating the polar routes over the North Pole since 2006 and 2009 respectively. CARI-6 and CARI-6M are commonly used space radiation estimation programs which are provided officially by the U.S. federal aviation administration (FAA). In this paper, the route doses and the annual radiation doses for Korean pilots and cabin crew were estimated by using CARI-6M based on 2012 flight records. Also the modeling concept was developed for our own space radiation estimation program which is composed of GEANT4 and NRLMSIS00 models. The GEANT4 model is used to trace the incident particle transports in the atmosphere and the NRLMSIS00 model is used to get the background atmospheric densities of various neutral atoms at the aircraft altitude. Also presented are the results of simple integration tests of those models and the plan to include the space weather variations through the solar proton event (SPE) prediction model such as UMASEP and the galactic cosmic ray (GCR) prediction model such as Badhwar-O'Neill 2010.

무연 방사선 차폐 시트에 대한 몬테카를로 전산모사 (Monte Carlo Simulation for Radiation Protection Sheets of Pb-Free)

  • 천권수
    • 한국방사선학회논문지
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    • 제11권4호
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    • pp.189-195
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    • 2017
  • 방사선 특히, 엑스선 또는 감마선으로부터 인체를 보호하기 위해 납(Pb)으로 된 보호 장구를 광범위하게 사용해왔다. 최근 납 중독 및 환경오염의 문제로 납을 대신하는 무연 방사선 차폐재의 개발이 활발히 이루어지고 있다. 차폐재의 성능 확보를 위해서는 제작 및 평가의 순환 사이클을 반복하게 된다. 본 연구는 실제 무연 방사선 차폐소재의 제작에 앞서 차폐재의 성능을 몬테카를로 전산모사를 통해 확인함으로써 가능한 차폐소재의 조합을 연구하였다. 방사선 차폐소재의 평가에 사용되는 조건으로 엑스선관을 Geant4를 이용하여 전산모사하고 획득된 광자 스펙트럼을 이용하여 텅스텐과 비스무스의 조합에 따른 차폐소재의 성능을 평가하였다. 차폐소재의 공극에 따른 성능 저하도 평가하였다. 방사선 차폐 소재 개발 시 공극률을 줄이는 것이 중요한 인자라는 것을 알 수 있었다.

Optimization of Energy Modulation Filter for Dual Energy CBCT Using Geant4 Monte-Carlo Simulation

  • Ju, Eun Bin;Ahn, So Hyun;Choi, Sang Gyu;Lee, Rena
    • 한국의학물리학회지:의학물리
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    • 제27권3호
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    • pp.125-130
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    • 2016
  • Dual energy computed tomography (DECT) is used to classify two materials and quantify the mass density of each material in the human body. An energy modulation filter based DECT could acquire two images, which are generated by the low- and high-energy photon spectra, in one scan, with one tube and detector. In the case of DECT using the energy modulation filter, the filter should perform the optimization process for the type of materials and thicknesses for generating two photon spectra. In this study, Geant4 Monte-Carlo simulation toolkit was used to execute the optimization process for determining the property of the energy modulation filter. In the process, various materials used for the energy modulation filter are copper (Cu, $8.96g/cm^3$), niobium (Nb, $8.57g/cm^3$), stannum (Sn, $7.31g/cm^3$), gold (Au, $19.32g/cm^3$), and lead (Pb, $11.34g/cm^3$). The thickness of the modulation filter varied from 0.1 mm to 1.0 mm. To evaluate the overlap region of the low- and high-energy spectrum, Geant4 Monte-Carlo simulation is used. The variation of the photon flux and the mean energy of photon spectrum that passes through the energy modulation filter are evaluated. In the primary photon spectrum of 80 kVp, the optimal modulation filter is a 0.1 mm lead filter that can acquire the same mean energy of 140 kVp photon spectrum. The lead filter of 0.1 mm based dual energy CBCT is required to increase the tube current 4.37 times than the original tube current owing to the 77.1% attenuation in the filter.

뇌 정위 방사선수술의 선량 계산을 위한 몬테카를로 시뮬레이션 코드 개발 (Development of Monte Carlo Simulation Code for the Dose Calculation of the Stereotactic Radiosurgery)

  • 강정구;이동준
    • 한국의학물리학회지:의학물리
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    • 제23권4호
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    • pp.303-308
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    • 2012
  • 뇌정위 방사선수술의 선량계산을 위해 Geant4 기반의 응용 프로그램을 개발 하였다. 선형가속기에서 발생하는 방사선의 스펙트럼을 입력하기 위하여 사전에 실행하여 구한 스펙트럼에 각 에너지별로 구한 가중치를 곱하여 확률밀도를 구하였다. 이를 누적밀도로 변환하여 입력하도록 하였다. 메신저 클래스를 이용하여 다양한 형태의 MLC 조사면을 설정할 수 있도록 하였다. 갠트리와 테이블의 회전을 모사하기 위하여 rotateX와 rotateY라는 회전행렬을 사용하였다. 월드좌표 속에서 갠트리와 테이블을 정의하여 각각 회전을 구현하였다. 실제 환자의 자료는 CT의 dicom 파일에서 픽셀 크기, 매트릭스 크기 등의 정보와 픽셀의 HU를 밀도로 변환한 파일을 생성한 다음 이 파일을 이용 환자의 모델링에 이용 하였다. 환자의 모델링은 팬텀월드 안에 픽셀의 크기에 해당하는 복셀을 정의하고 이 복셀에 픽셀의 밀도와 이 밀도에 해당하는 물질을 할당해주었다.

Bragg-curve simulation of carbon-ion beams for particle-therapy applications: A study with the GEANT4 toolkit

  • Hamad, Morad Kh.
    • Nuclear Engineering and Technology
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    • 제53권8호
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    • pp.2767-2773
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    • 2021
  • We used the GEANT4 Monte Carlo MC Toolkit to simulate carbon ion beams incident on water, tissue, and bone, taking into account nuclear fragmentation reactions. Upon increasing the energy of the primary beam, the position of the Bragg-Peak transfers to a location deeper inside the phantom. For different materials, the peak is located at a shallower depth along the beam direction and becomes sharper with increasing electron density NZ. Subsequently, the generated depth dose of the Bragg curve is then benchmarked with experimental data from GSI in Germany. The results exhibit a reasonable correlation with GSI experimental data with an accuracy of between 0.02 and 0.08 cm, thus establishing the basis to adopt MC in heavy-ion treatment planning. The Kolmogorov-Smirnov K-S test further ascertained from a statistical point of view that the simulation data matched the experimentally measured data very well. The two-dimensional isodose contours at the entrance were compared to those around the peak position and in the tail region beyond the peak, showing that bone produces more dose, in comparison to both water and tissue, due to secondary doses. In the water, the results show that the maximum energy deposited per fragment is mainly attributed to secondary carbon ions, followed by secondary boron and beryllium. Furthermore, the number of protons produced is the highest, thus making the maximum contribution to the total dose deposition in the tail region. Finally, the associated spectra of neutrons and photons were analyzed. The mean neutron energy value was found to be 16.29 MeV, and 1.03 MeV for the secondary gamma. However, the neutron dose was found to be negligible as compared to the total dose due to their longer range.