Development of a dose estimation code for BNCT with GPU accelerated Monte Carlo and collapsed cone Convolution method
0
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
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
Abstract
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
참고문헌 (31)
- R. F. Barth, "Boron delivery agents for neutron capture therapy of cancer", Cancer Commun, 38, pp.1~15 (2018)[DOI]
- I. Kato, "Effectiveness of BNCT for recurrent head and neck malignancies", Appl. Radiat. Isot, 61, pp.1069~1073 (2004)[DOI]
- Y. C. Lin, "Similar T", N ratio between 18F-FBPA diagnostic and BPA therapeutic dosages for boron neutron capture therapy in orthotropic tongue cancer model, 2020, pp.34, 58~64
- S. Miyatake, "Clinical results of BNCT for malignant meningiomas", Adv. Neutron Capture Ther. 2006 Proc. 12th Int. Congr. Neutron Capture Ther, pp.638~ (2006)
- E. Bavarnegin, "Neutron beams implemented at nuclear research reactors for BNCT", J. Instrum, 12 (2017)
- B. Vanderstraeten, "Accuracy of patient dose calculation for lung IMRT: a comparison of Monte Carlo, convolution", superposition, and pencil beam computations, 2006, pp.33, 3149~3158
- R. G. Zamenhof, "Monte Carlo-based treatment planning for boron neutron capture therapy using custom designed models automatically generated from CT data", Int. J. Radiat. Oncol. Biol. Phys, 35, pp.383~397 (1996)[DOI]
- D. Nigg, "SERA – an advanced treatment planning system for neutron therapy and BNCT", Trans. Am. Nucl. Soc, 80 (1999)
- H. Kumada, "Development of JCDS, a computational dosimetry system at JAEA for boron neutron capture therapy", J. Phys. Conf. Ser, 74 (2007)
- K. Takada, "Development of Monte Carlo based real-time treatment planning system with fast calculation algorithm for boron neutron capture therapy", Phys. Med, 32, pp.1846~1851 (2016)
- H. Kumada, "Improvement of dose calculation accuracy for BNCT dosimetry by the multi-voxel method in JCDS", Appl. Radiat. Isot, 61, pp.1045~1050 (2004)[DOI]
- B. J. Albertson, "An investigation on the use of removal-diffusion theory for BNCT treatment planning : a method for determining proper removal-diffusion parameters", Med. Phys, 28, pp.1898~1904 (2001)[DOI]
- A. Badal, "Accelerating Monte Carlo simulations of photon transport in a voxelized geometry using a massively parallel graphics processing unit", Med. Phys, 36, pp.4878~4880 (2009)[DOI]
- X. Jia, "GPU-based fast Monte Carlo dose calculation for proton therapy", Phys. Med. Biol, 57, pp.7783~7797 (2012)[DOI]
- G. Battistoni, "Overview of the FLUKA code", Ann. Nucl. Energy, 82, pp.10~18 (2015)[DOI]
- "release: 10.2.89" (2020)[URL]
- U. Schneider, "The calibration of CT Hounsfield units for RTP", Phys. Med. Biol, 41, pp.111~124 (1996)
- Å. K. Carlsson, "The collapsed cone superposition algorithm applied to scatter dose calculations in brachytherapy", Med. Phys, 27, pp.2320~2332 (2000)[DOI]
- C. R. Harris, "Array programming with {NumPy", Nature, 585, pp.357~362 (2020)[DOI]
- "{SciPy}: Open source scientific tools for {Python}"[URL]
- J. Sanders, "CUDA by Example an Introduction to General-Purpose GPU Programming", Addison-Wesley Professional (2010)
- S. P. Hamilton, "Continuous-energy Monte Carlo neutron transport on GPUs in the Shift code", Ann. Nucl. Energy, 128, pp.236~247 (2019)[DOI]
- F. B. Brown, "Monte Carlo methods for radiation transport analysis on vector computers", Prog. Nucl. Energy, 14, pp.269~299 (1984)[DOI]
- I. Lux, "Monte Carlo Particle Transport Methods: Neutron and Photon Calculations" (2018), CRC press
- D. A. Brown, "ENDF", B-VIII.0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data, 2018, pp.148, 1~142
- X. X. Cai, "Rejection-based sampling of inelastic neutron scattering", J. Comput. Phys, 380, pp.400~407 (2019)[DOI]
- A. Ahnesj€o, "Calculation and application of point spread functions for treatment planning with high energy photon beams", Acta Oncol. (Madr. ), 26, pp.49~56 (1987)[DOI]
- A. Gonz"alez, "Measurement of areas on a sphere using Fibonacci and latitudelongitude lattices", Math. Geosci, 42, pp.49~64 (2010)[DOI]
- J. Amanatides, "A fast voxel traversal algorithm for ray tracing", Eurographics, 87, pp.3~10 (1987)
- 조웅, "Practical Implementation of a Collapsed Cone Convolution Algorithm for a Radiation Treatment Planning System", Journal of the Korean Physical Society, 61(12), pp.2073~2083 (2012), 한국물리학회
- I. Auterinen, "Measurement of free beam neutron spectra at eight BNCT facilities worldwide", Appl. Radiat. Isot, 61, pp.1021~1026 (2004)[DOI]
