Development of ARCHER -- a Parallel Monte Carlo Radiation Transport Code -- for X-ray CT Dose Calculations Using GPU and Coprocessor Technologies PDF Download

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Development of ARCHER -- a Parallel Monte Carlo Radiation Transport Code -- for X-ray CT Dose Calculations Using GPU and Coprocessor Technologies

Development of ARCHER -- a Parallel Monte Carlo Radiation Transport Code -- for X-ray CT Dose Calculations Using GPU and Coprocessor Technologies PDF Author: Tianyu Liu
Publisher:
ISBN:
Category :
Languages : en
Pages : 228

Book Description


Development of ARCHER -- a Parallel Monte Carlo Radiation Transport Code -- for X-ray CT Dose Calculations Using GPU and Coprocessor Technologies

Development of ARCHER -- a Parallel Monte Carlo Radiation Transport Code -- for X-ray CT Dose Calculations Using GPU and Coprocessor Technologies PDF Author: Tianyu Liu
Publisher:
ISBN:
Category :
Languages : en
Pages : 228

Book Description


Development of a Fast Monte Carlo Code for Dose Calculation in a Treatment Planning and Feasibility Study of High Contrast Portal Imaging

Development of a Fast Monte Carlo Code for Dose Calculation in a Treatment Planning and Feasibility Study of High Contrast Portal Imaging PDF Author: Keivan Jabbari Najafabadi
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
A fast and accurate treatment planning system is essential for radiation therapy and Monte Carlo (MC) techniques produce the most accurate results for dose calculation in treatment planning. In this work, we developed a fast Monte Carlo code based on pre-calculated data (PMC, Pre-calculated Monte Carlo) for applications in radiation therapy treatment planning. The PMC code takes advantage of large available memory in current computer hardware for extensive generation of pre-calculated data. Primary tracks of electrons are generated in the middle of homogeneous materials (water, air, bone, lung) and with energies between 0.2 and 18 MeV using the EGSnrc code. Secondary electrons are not transported but their position, energy, charge and direction are saved and used as a primary particle. Based on medium type and incident electron energy, a track is selected from the pre-calculated set. The performance of the method is tested in various homogeneous and heterogeneous configurations and the results were generally within 2% compared to EGSnrc but with a 40-60 times speed improvement. Pre-calculated Monte Carlo codes are accurate, fast and physics-independent and therefore applicable to different radiation types including heavy-charged particles. In another project, we worked on Monte Carlo feasibility study to use orthogonal bremsstrahlung beams for imaging in radiation therapy. The basic characteristics of orthogonal bremsstrahlung beams are studied and the feasibility of improved contrast imaging in linear accelerator with such a beam is evaluated. In the context of this work orthogonal bremsstrahlung beams represent the component of the bremsstrahlung distribution perpend.

Progress Report on the Development of a Large-scale Conditional Consistent Economic and Manpower Forecasting Model

Progress Report on the Development of a Large-scale Conditional Consistent Economic and Manpower Forecasting Model PDF Author: David J. Kuck
Publisher:
ISBN:
Category : Assembler language (Computer program language).
Languages : en
Pages : 31

Book Description


Monte Carlo Dose Verification of an X-ray Beam in a Virtual Water Phantom

Monte Carlo Dose Verification of an X-ray Beam in a Virtual Water Phantom PDF Author: Virginia Maniquis
Publisher:
ISBN:
Category : Linear accelerators
Languages : en
Pages :

Book Description
Monte Carlo (MC) methods are widely accepted as the most accurate technique for calculating dose distributions in radiation therapy physics. Simulating the particle transport through the treatment head of a linear accelerator utilizing a MC based code is both a widespread and practical approach to determining detailed clinical beam characteristics such as the energy, angular and spatial distribution of particles which are needed to properly quantify dose. One particular and versatile MC code, the Monte Carlo N-Particle (MCNP) radiation transport code, developed by Los Alamos National Laboratory, has been commonly used to model ionizing radiations for medical physics applications. In this thesis, a Varian 2100C linear accelerator (linac) is modeled and the electron and photon transport through the primary components of the treatment head are simulated using MCNP Version 5_1.3. The 6 MV photon spectra was characterized in a standard 10 x 10 cm2 field and subsequent dose calculations were made in a Virtual Water (VW) phantom. Energy fluence, percent depth dose and beam profile measurements were taken in a modeled VW phantom and the calculated data was compared to measured reference data. In addition, a human phantom was modeled for future dose calculations using the modeled linac. The linac model created can incorporate different beam energies for determining the dose distribution of multiple beam treatments in phantoms for standard 6 MV plans. The adaptability of this MCNP model allows for any number of geometries and sources encountered in medical physics to be computed and applied with relative ease. Future studies can involve adding complex multi-leaf collimator beam shaping and calculating the dose in human phantom models, which would serve as a basis for studies involving MCNP modeling for dose optimization in medical physics applications.

Implementation, Capabilities, and Benchmarking of Shift, a Massively Parallel Monte Carlo Radiation Transport Code

Implementation, Capabilities, and Benchmarking of Shift, a Massively Parallel Monte Carlo Radiation Transport Code PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 34

Book Description
This paper discusses the implementation, capabilities, and validation of Shift, a massively parallel Monte Carlo radiation transport package developed and maintained at Oak Ridge National Laboratory. It has been developed to scale well from laptop to small computing clusters to advanced supercomputers. Special features of Shift include hybrid capabilities for variance reduction such as CADIS and FW-CADIS, and advanced parallel decomposition and tally methods optimized for scalability on supercomputing architectures. Shift has been validated and verified against various reactor physics benchmarks and compares well to other state-of-the-art Monte Carlo radiation transport codes such as MCNP5, CE KENO-VI, and OpenMC. Some specific benchmarks used for verification and validation include the CASL VERA criticality test suite and several Westinghouse AP1000® problems. These benchmark and scaling studies show promising results.

Optimized Computation of Radiation Transport in Complex Multi-material Targets

Optimized Computation of Radiation Transport in Complex Multi-material Targets PDF Author: Defence Research Establishment Ottawa
Publisher:
ISBN:
Category :
Languages : en
Pages : 7

Book Description


Development and Application of a GPU-based Fast Electron-photon Coupled Monte Carlo Code for Radiation Therapy

Development and Application of a GPU-based Fast Electron-photon Coupled Monte Carlo Code for Radiation Therapy PDF Author: Lin Su
Publisher:
ISBN:
Category :
Languages : en
Pages : 164

Book Description


Applications of the COG Multiparticle Monte Carlo Transport Code to Simulated Imaging of Complex Objects

Applications of the COG Multiparticle Monte Carlo Transport Code to Simulated Imaging of Complex Objects PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
COG is a major multiparticle simulation code in the LLNL Monte Carlo radiation transport toolkit. It was designed to solve deep-penetration radiation shielding problems in arbitrarily complex 3D geometries, involving coupled transport of photons, neutrons, and electrons. COG was written to provide as much accuracy as the underlying cross-sections will allow, and has a number of variance-reduction features to speed computations. Recently COG has been applied to the simulation of high- resolution radiographs of complex objects and the evaluation of contraband detection schemes. In this paper we will give a brief description of the capabilities of the COG transport code and show several examples of neutron and gamma-ray imaging simulations. Keywords: Monte Carlo, radiation transport, simulated radiography, nonintrusive inspection, neutron imaging.

Patient-specific Dose Calculations in X-ray Computed Tomography Using Monte Carlo Methods

Patient-specific Dose Calculations in X-ray Computed Tomography Using Monte Carlo Methods PDF Author: Paul Deak
Publisher:
ISBN:
Category :
Languages : en
Pages : 188

Book Description


New Parallel Computing Framework for Radiation Transport Codes

New Parallel Computing Framework for Radiation Transport Codes PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 6

Book Description
A new parallel computing framework has been developed to use with general-purpose radiation transport codes. The framework was implemented as a C++ module that uses MPI for message passing. The module is significantly independent of radiation transport codes it can be used with, and is connected to the codes by means of a number of interface functions. The framework was integrated with the MARS15 code, and an effort is under way to deploy it in PHITS. Besides the parallel computing functionality, the framework offers a checkpoint facility that allows restarting calculations with a saved checkpoint file. The checkpoint facility can be used in single process calculations as well as in the parallel regime. Several checkpoint files can be merged into one thus combining results of several calculations. The framework also corrects some of the known problems with the scheduling and load balancing found in the original implementations of the parallel computing functionality in MARS15 and PHITS. The framework can be used efficiently on homogeneous systems and networks of workstations, where the interference from the other users is possible.