Download or read book Validation of a Monte Carlo Code for Radiation Streaming Analyses written by N. De Gangi and published by . This book was released on 1980 with total page 100 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book NUREG CR written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1980 with total page 100 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Validation of the GEANT4 Monte Carlo Code for Radiotherapy Applications written by Emily S. Poon and published by . This book was released on 2004 with total page 302 pages. Available in PDF, EPUB and Kindle. Book excerpt: "GEANT4 is a Monte Carlo code developed in an object-oriented environment. It provides three models of electromagnetic physics, namely Standard, Low-energy, and Penelope. In this work, we examined the accuracy of the photon and electron interactions, and developed a user code for external beam radiotherapy simulations. The code has the capabilities to collect phase space data, perform variance reduction schemes, and calculate dose distributions in a phantom. For all three models, the dose distributions of monoenergetic and clinical photon beams in water are in good agreement with the EGSnrc simulations. For electron beams, the results depend on the maximum electron step size. Significant step size artifacts are also found in the transport of electrons through a thin aluminum slab. Our studies of interface perturbation effects and Fano cavity response illustrated potential problems with the condensed history algorithm. Overall, GEANT4 can be used in applications where electron transport is not critical." --
Download or read book Experimental Validation and Evaluation of Uncertainty in the Monte Carlo Modeling of Electron Irradiation of Complex Objects written by Teresa Elizabeth Tutt and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Monte Carlo method is an invaluable tool in the field of radiation protection, used to calculate shielding effectiveness, as well as dose for medical applications. With few exceptions, most of the objects currently simulated have been homogeneous materials that vary in density by a factor of 3 or less. In the irradiation of very heterogeneous objects, particularly layered or leafy food items, one will encounter air pockets within the bundle as a matter of course. These pockets will cause variations in density of up to three orders of magnitude. Air pockets in a tissue equivalent phantom were found to produce "hot spots" in the dose distribution, and introduced significant deviations between the calculated and measured distribution of dose to the phantom. To date, very little published work had been done in the area of Monte-Carlo simulation of objects of such disparate density. Before Monte Carlo methods can be used successfully in this regime, further code development and experimental validation will be necessary, of which this work is just a beginning. Phantoms were made of corrugated low-Z material similar in electron density to plant based material. These phantoms incorporated air gaps of comparable size to those found in the leafy objects of interest. Dimensions were chosen to bracket electron ranges in the material of the objects modeled. Monte Carlo analysis will provide a reasonable qualitative picture of the dose distribution, but such a picture is not yet sufficiently accurate in a quantitative sense. Air gaps within the plant material produced large discrepancies between calculation and measurement. Smaller air gaps were observed to produce greater discrepancy between calculation and measurement.
Download or read book A Monte Carlo Primer written by Stephen A. Dupree and published by Springer Science & Business Media. This book was released on 2012-09-07 with total page 348 pages. Available in PDF, EPUB and Kindle. Book excerpt: The mathematical technique of Monte Carlo, as applied to the transport of sub-atomic particles, has been described in numerous reports and books since its formal development in the 1940s. Most of these instructional efforts have been directed either at the mathematical basis of the technique or at its practical application as embodied in the several large, formal computer codes available for performing Monte Carlo transport calculations. This book attempts to fill what appears to be a gap in this Monte Carlo literature between the mathematics and the software. Thus, while the mathematical basis for Monte Carlo transport is covered in some detail, emphasis is placed on the application of the technique to the solution of practical radiation transport problems. This is done by using the PC as the basic teaching tool. This book assumes the reader has a knowledge of integral calculus, neutron transport theory, and Fortran programming. It also assumes the reader has available a PC with a Fortran compiler. Any PC of reasonable size should be adequate to reproduce the examples or solve the exercises contained herein. The authors believe it is important for the reader to execute these examples and exercises, and by doing so to become accomplished at preparing appropriate software for solving radiation transport problems using Monte Carlo. The step from the software described in this book to the use of production Monte Carlo codes should be straightforward.
Download or read book Verification of a Monte Carlo Code System for Analysis of Ionization Chamber Responses written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this work was the development and testing of a Monte Carlo code system for calculating an ionization chamber response to a mixed neutron and photon radiation environment. The resulting code system entitled MICAP - a Monte Carlo Ionization Chamber Analysis Package - determines the neutron, photon, and total response of the Ionization chamber to the mixed field radiation environment. To demonstrate the ability of MICAP, comparisons were made with existing code systems and experimental results. Comparisons with existing code systems verified the accuracy of the neutron, photon, and charged particle transport processes and the nuclear models used to describe the individual neutron reactions. Comparisons with monoenergetic photon calibration experiments and mixed neutron and photon radiation experiments verified the applicability of MICAP for analysis of ionization chamber responses to mixed field radiation environments. The major conclusion of the study is that MICAP represents a unique capability in the area of ionization chamber response analysis and is expected to be useful for many applications in the field of radiation dosimetry. 11 refs., 4 figs., 2 tabs.
Download or read book Advanced Monte Carlo for Radiation Physics Particle Transport Simulation and Applications written by Andreas Kling and published by Springer Science & Business Media. This book was released on 2014-02-22 with total page 1200 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book focuses on the state of the art of Monte Carlo methods in radiation physics and particle transport simulation and applications. Special attention is paid to algorithm development for modeling, and the analysis of experiments and measurements in a variety of fields.
Download or read book Development of a New Monte Carlo Reactor Physics Code written by Jaakko Leppänen and published by . This book was released on 2007 with total page 236 pages. Available in PDF, EPUB and Kindle. Book excerpt: Monte Carlo neutron transport codes are widely used in various reactor physics applications, traditionally related to criticality safety analyses, radiation shielding problems, detector modelling and validation of deterministic transport codes. The main advantage of the method is the capability to model geometry and interaction physics without major approximations. The disadvantage is that the modelling of complicated systems is very computing-intensive, which restricts the applications to some extent. The importance of Monte Carlo calculation is likely to increase in the future, along with the development in computer capacities and parallel calculation. An interesting near-future application for the Monte Carlo method is the generation of input parameters for deterministic reactor simulator codes. These codes are used in coupled LWR full-core analyses and typically based on fewgroup nodal diffusion methods. The input data consists of homogenised fewgroup constants, presently generated using deterministic lattice transport codes. The task is becoming increasingly challenging, along with the development in nuclear technology. Calculations involving high-burnup fuels, advanced MOX technology and next-generation reactor systems are likely to cause problems in the future, if code development cannot keep up with the applications. A potential solution is the use of Monte Carlo based lattice transport codes, which brings all the advantages of the calculation method. So far there has been only a handful of studies on group constant generation using the Monte Carlo method, although the interest has clearly increased during the past few years. The homogenisation of reaction cross sections is simple and straightforward, and it can be carried out using any Monte Carlo code. Some of the parameters, however, require the use of special techniques that are usually not available in general-purpose codes. The main problem is the calculation of neutron diffusion coefficients, which have no continuous-energy counterparts in the Monte Carlo calculation. This study is focused on the development of an entirely new Monte Carlo neutron transport code, specifically intended for reactor physics calculations at the fuel assembly level. The PSG code is developed at VTT Technical Research Centre of Finland and one of the main applications is the generation of homogenised group constants for deterministic reactor simulator codes. The theoretical background on general transport theory, nodal diffusion calculation and the Monte Carlo method are discussed. The basic methodology used in the PSG code is introduced and previous studies related to the topic are briefly reviewed. PSG is validated by comparison to reference results produced by MCNP4C and CASMO-4E in infinite two-dimensional LWR lattice calculations. Group constants generated by PSG are used in ARES reactor simulator calculations and the results compared to reference calculations using CASMO-4E data.
Download or read book Monthly Catalog of United States Government Publications written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Safety written by and published by . This book was released on 1979 with total page 864 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Regulatory and Technical Reports written by U.S. Nuclear Regulatory Commission. Policy and Publications Management Branch and published by . This book was released on 1981 with total page 192 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Monte Carlo Methods for Radiation Transport written by Oleg N. Vassiliev and published by Springer. This book was released on 2016-10-17 with total page 292 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is a guide to the use of Monte Carlo techniques in radiation transport. This topic is of great interest for medical physicists. Praised as a "gold standard" for accurate radiotherapy dose calculations, Monte Carlo has stimulated a high level of research activity that has produced thousands of papers within the past few years. The book is designed primarily to address the needs of an academically inclined medical physicist who wishes to learn the technique, as well as experienced users of standard Monte Carlo codes who wish to gain insight into the underlying mathematics of Monte Carlo algorithms. The book focuses on the fundamentals—giving full attention to and explaining the very basic concepts. It also includes advanced topics and covers recent advances such as transport of charged particles in magnetic fields and the grid-based solvers of the Boltzmann equation.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1993-08 with total page 472 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Monte Carlo Simulation of Radiation Streaming from a Radioactive Material Shipping Cask written by and published by . This book was released on 1996 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Regulatory and Technical Reports written by U.S. Nuclear Regulatory Commission. Division of Technical Information and Document Control and published by . This book was released on 1980 with total page 596 pages. Available in PDF, EPUB and Kindle. Book excerpt: Includes indexes.
Download or read book Proceedings of the National Symposium on Natural and Manmade Radiation in Space Held at Las Vegas Nevada March 1 5 1971 written by E. A. Warman and published by . This book was released on 1972 with total page 1044 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Monthly Catalogue United States Public Documents written by and published by . This book was released on 1982 with total page 1094 pages. Available in PDF, EPUB and Kindle. Book excerpt:
