Nelson | Computer Techniques in Radiation Transport and Dosimetry | Buch | 978-1-4684-3610-5 | www.sack.de

Buch, Englisch, 521 Seiten, Format (B × H): 170 mm x 244 mm, Gewicht: 914 g

Reihe: Physical Sciences

Nelson

Computer Techniques in Radiation Transport and Dosimetry


1. Auflage 2012
ISBN: 978-1-4684-3610-5
Verlag: Springer

Buch, Englisch, 521 Seiten, Format (B × H): 170 mm x 244 mm, Gewicht: 914 g

Reihe: Physical Sciences

ISBN: 978-1-4684-3610-5
Verlag: Springer


In October 1978, a group of 41 scientists from 14 countries met in Erice, Sicily to attend the Second Course of the Interna tional School of Radiation Damage and Protection "Ettore Majorana", the proceedings of which are contained in this book. The countries represented at the School were: Brazil, Canada, Federal Republic of Germany, Finland, German Democratic Republic, Hungary, India, Italy, Japan, Spain, Sweden, Switzerland, United States of America, and Yugoslavia. The School was officially sponsored by the Italian Health Physics Association, the Italian Ministry of Public Education, the Italian Ministry of Scientific and Technological Research, and the Sicilian Regional Government. In addition, administrative and tech nical support was received from the Stanford Linear Accelerator Center and from CERN. The past 15 or so years have witnessed a significant develop ment of computer methods in the science of radiation protection. The radiation transport codes associated with hadronic and electro magnetic cascades, reactor shielding, unfolding techniques, and gamma ray spectrum analysis have reached the state-of-the-art level, and the Erice Course aimed at presenting as comprehensive an over view of these programs as was possible within the allotted time span.

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Introductory Lectures.- Lecture 1: Computer Methods in Radiation Protection as Viewed by a User.- Lecture 2: The Physics of Radiation Transport.- Low Energy Neutron and Gamma-Ray Programs and Their Applications.- Lecture 3: The Methods and Applications of Discrete Ordinates in Low Energy Neutron- Photon Transport (ANISN, DOT) Part I: Methods.- Lecture 4: The Methods and Applications of Monte Carlo in Low Energy (? 20 MeV) Neutron- Photon Transport (MORSE) Part Is Methods.- Lecture 5: The Methods and Applications of Discrete Ordinates in Low Energy Neutron-Photon Transport (ANISN, DOT) Part II: Applications.- Lecture 6: The Methods and Applications of Monte Carlo in Low Energy (? 20 MeV) Neutron-Photon Transport (MORSE) Part II: Applications.- Lecture 7: The European Shielding Information Service — ESIS.- Lecture 8: Cross Section Processing Codes and Data Bases (AMPX).- Lecture 9: Radiation Shielding Information Center and Biomedical Computing Technology Information Center.- Lecture 10: Approximate Methods in Reactor Shielding Calculations.- Electromagnetic Cascade Shower Programs and Their Applications.- Lecture 11: The Physics of Electromagnetic Cascade.- Lecture 12: Solution of the Electromagnetic Cascade Shower Problem by Analog Monte Carlo Methods — EGS.- Lecture 13: Some Examples for the Application of the Monte Carlo Code EGS.- Lecture 14: Calculation of the Average Properties of Electromagnetic Cascades at High Energies (AEGIS).- Lecture 15: Electron Dosimetry Using Monte Carlo Techniques.- Lecture 16: Application of EGS to Detector Design in High Energy Physics.- Lecture 17: Application of EGS and ETRAN to Problems in Medical Physics and Dosimetry.- Hadronic Cascade Programs and Their Applications.- Lecture 18: Introduction to Hadronic Cascades.- Lecture19: Particle Production Models, Sampling High-Energy Multiparticle Events from Inclusive Single-Particle Distributions.- Lecture 20: The Intranuclear-Cascade-Evaporation Model.- Lecture 21: Calculation of the Average Properties of Hadronic Cascades at High Energies (CASIM).- Lecture 22: The FLUKA and KASPRO Hadronic Cascade Codes.- Lecture 23: The HETC Hadronic Cascade Code.- Unfolding Methods and Spectrum Analysis.- Lecture 24: Unfolding Techniques for Activation Detector Analysis.- Lecture 25: BremsStrahlung Spectrum Analysis by Activation Method (LYRA, DIBRE, REFUM).- Lecture 26: Application of Activation-Spectrum Analysis Method to Shielding (TAURUS, LYRA, DIBRE, SAND-II).- Lecture 27: Activation Detectors and Their Gamma Spectrum Analysis.- Invited Presentations from Students and Summary Lecture.- Monte Carlo Calculation of Exposure Rates in Dwelling Rooms.- Integral Equation for Radiation Transport — ASFIT.- Thermal Effects Induced by High Energy Protons in Target and Absorber Materials.- Summary Lecture.- Participants.



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