Epithermal Neutron Beam Design at the Oregon State University TRIGA Mark II Reactor (OSTR) Based on Monte Carlo Methods PDF Download

Author: Kanokrat Tiyapun
Publisher:
ISBN:
Category : Boron-neutron capture therapy
Languages : en
Pages : 282

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Author: American Nuclear Society
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 760

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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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The Monte Carlo Model System (MCMS) for the Washington State University (WSU) Radiation Center provides a means through which core criticality and power distributions can be calculated, as well as providing a method for neutron and photon transport necessary for BNCT epithermal neutron beam design. The computational code used in this Model System is MCNP4A. The geometric capability of this Monte Carlo code allows the WSU system to be modeled very accurately. A working knowledge of the MCNP4A neutron transport code increases the flexibility of the Model System and is recommended, however, the eigenvalue/power density problems can be run with little direct knowledge of MCNP4A. Neutron and photon particle transport require more experience with the MCNP4A code. The Model System consists of two coupled subsystems; the Core Analysis and Source Plane Generator Model (CASP), and the BeamPort Shell Particle Transport Model (BSPT). The CASP Model incorporates the S([alpha], [beta]) thermal treatment, and is run as a criticality problem yielding, the system eigenvalue (k[sub eff]), the core power distribution, and an implicit surface source for subsequent particle transport in the BSPT Model. The BSPT Model uses the source plane generated by a CASP run to transport particles through the thermal column beamport. The user can create filter arrangements in the beamport and then calculate characteristics necessary for assessing the BNCT potential of the given filter want. Examples of the characteristics to be calculated are: neutron fluxes, neutron currents, fast neutron KERMAs and gamma KERMAs. The MCMS is a useful tool for the WSU system. Those unfamiliar with the MCNP4A code can use the MCMS transparently for core analysis, while more experienced users will find the particle transport capabilities very powerful for BNCT filter design.

Author: Simon Kellman
Publisher:
ISBN:
Category : FORTRAN II (Computer program language)
Languages : en
Pages : 110

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Author: J. R. Streetman
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 86

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Author: Jerome Spanier
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 72

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Book Description

Author: H. Zaidi
Publisher: CRC Press
ISBN: 1000687686
Category : Medical
Languages : en
Pages : 441

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Book Description
Therapeutic Applications of Monte Carlo Calculations in Nuclear Medicine examines the applications of Monte Carlo (MC) calculations in therapeutic nuclear medicine, from basic principles to computer implementations of software packages and their applications in radiation dosimetry and treatment planning. With chapters written by recognized authorit

Author: W. E. Kinney
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 38

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Author: Russell V. Parrish
Publisher:
ISBN:
Category : Mathematical optimization
Languages : en
Pages : 52

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An algorithm employing a modified sequential random perturbation, or creeping random search, was applied to the problem of optimizing the parameters of a high-energy beam transport system. The stochastic solution of the mathematical model for first-order magnetic-field expansion allows the inclusion of state-variable constraints, and the inclusion of parameter constraints allowed by the method of algorithm application eliminates the possibility of infeasible solutions. The mathematical model and the algorithm were programmed for a real-time simulation facility; thus, two important features are provided to the beam designer: (1) a strong degree of man-machine communication (even to the extent of bypassing the algorithm and applying analog-matching techniques), and (2) extensive graphics for displaying information concerning both algorithm operation and transport-system behavior. Chromatic aberration was also included in the mathematical model and in the optimization process. Results presented show this method as yielding better solutions (in terms of resolutions) to the particular problem than those of a standard analog program as well as demonstrating flexibility, in terms of elements, constraints, and chromatic aberration, allowed by user interaction with both the algorithm and the stochastic model. Example of slit usage and a limited comparison of predicted results and actual results obtained with a 600 MeV cyclotron are given.

Author: Joe R. Beeler (Jr.)
Publisher:
ISBN:
Category : Gamma rays
Languages : en
Pages : 18

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