지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2022.5
- 수록면
- 1,769 - 1,780 (12page)
- DOI
- https://doi.org/10.1016/j.net.2021.11.010
이용수
이 논문의 연구 히스토리 (2)
- 이 논문의 후속연구가 궁금하신가요?
- 연관 학술논문 또는 학술발표를 통해 보다 발전된 연구결과를 확인하실 수 있습니다.
- 이 논문의 연구 히스토리 확인하기
초록· 키워드
오류제보하기
A new method of dose calculation algorithm, called GPU-accelerated Monte Carlo and collapsed coneConvolution (GMCC) was developed to improve the calculation speed of BNCT treatment planning system. The GPU-accelerated Monte Carlo routine in GMCC is used to simulate the neutron transport overwhole energy range and the Collapsed Cone Convolution method is to calculate the gamma dose. Otherdose components due to alpha particles and protons, are calculated using the calculated neutron flux andreaction data. The mathematical principle and the algorithm architecture are introduced. The accuracyand performance of the GMCC were verified by comparing with the FLUKA results. A water phantom anda head CT voxel model were simulated. The neutron flux and the absorbed dose obtained by the GMCCwere consistent well with the FLUKA results. In the case of head CT voxel model, the mean absolutepercentage error for the neutron flux and the absorbed dose were 3.98% and 3.91%, respectively. Thecalculation speed of the absorbed dose by the GMCC was 56 times faster than the FLUKA code. It wasverified that the GMCC could be a good candidate tool instead of the Monte Carlo method in the BNCTdose calculations
목차
등록된 정보가 없습니다.
참고문헌 (0)
참고문헌 신청함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
An Assessment of the Secondary Neutron Dose in the Passive Scattering Proton Beam Facility of the National Cancer Center
Nuclear Engineering and Technology
2017 .06
-
Evaluation of the medical staff effective dose during boron neutron capture therapy using two high resolution voxel-based whole body phantoms
Nuclear Engineering and Technology
2017 .01
-
Monte Carlo shielding evaluation of a CSNS Multi-Physics instrument
Nuclear Engineering and Technology
2019 .01
-
Evaluation of dose distribution from 12C ion in radiation therapy by FLUKA code
Nuclear Engineering and Technology
2020 .10
-
Neutron activation analysis: Modelling studies to improve the neutron flux of Americiume-Beryllium source
Nuclear Engineering and Technology
2017 .06
-
Strain‑Dependent Polar Optical Phonon Scattering and Drive Current Optimization in Nanoscale Monolayer MoS2 FETs
Electronic Materials Letters
2020 .01
-
Organ dose conversion coefficients in CT scans for Korean adult males and females
Nuclear Engineering and Technology
2022 .02
-
Monte Carlo simulation and optimization of neutron ray shielding performance of related materials
Nuclear Engineering and Technology
2024 .09
-
Limits on the efficiency of event-based algorithms for Monte Carlo neutron transport
Nuclear Engineering and Technology
2017 .01
-
Clustering and traveling waves in the Monte Carlo criticality simulation of decoupled and confi ned media
Nuclear Engineering and Technology
2017 .01
-
Calculation of thermal neutron scattering data of MgF2 and its effect on beam shaping assembly for BNCT
Nuclear Engineering and Technology
2023 .04
-
Monte-Carlo 시뮬레이션 기반 Power Curve의 전력변환 오차 개선에 관한 연구
대한전기학회 학술대회 논문집
2019 .07
-
Optimization of Target, Moderator, and Collimator in the Accelerator-based Boron Neutron Capture Therapy System: A Monte Carlo Study
Nuclear Engineering and Technology
2021 .06
-
Applicability of the Kr ? ko nuclear power plant core Monte Carlo model for the determination of the neutron source term
Nuclear Engineering and Technology
2021 .11
-
Neutron clustering in Monte Carlo iterated-source calculations
Nuclear Engineering and Technology
2017 .01
-
Electron Accelerator Shielding Design of KIPT Neutron Source Facility
Nuclear Engineering and Technology
2016 .06
-
In-line (α,n) source sampling methodology for monte carlo radiation transport simulations
Nuclear Engineering and Technology
2017 .01
-
Thermal neutron albedo and flux for different geometries neutron guide
Nuclear Engineering and Technology
2019 .01
-
Domain decomposition for GPU-Based continuous energy Monte Carlo power reactor calculation
Nuclear Engineering and Technology
2020 .11
-
표준태풍 생성을 위한 Monte-Carlo 시뮬레이션
대한토목학회 학술대회
2015 .10
이 논문의 저자 정보
최근 본 자료
댓글(0)
0