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Titlebook: Computer Techniques in Radiation Transport and Dosimetry; Walter R. Nelson,Theodore M. Jenkins Book 1980 Springer Science+Business Media N

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51#
發(fā)表于 2025-3-30 09:51:21 | 只看該作者
52#
發(fā)表于 2025-3-30 14:25:31 | 只看該作者
,Giv‘a(chǎn)t ?avivah and Ulpan ‘A?iva,the physics is the same), can be used rather effectively in problems dealing with: 1) photon scattering at low energies (i.e., synchrotron radiation); 2) cascades within and behind absorbers (i.e., beam dumps); 3) dose and shielding parameters of stray electron-photon radiation from a high energy electron accelerator.
53#
發(fā)表于 2025-3-30 18:38:34 | 只看該作者
The Physics of Radiation Transportmann in 1872 to study the properties of gases. It applies equally to the description of the behavior of “radiation” which, for the purpose of this paper, will comprise nuclei, leptons, mesons, baryons, and energetic photons.
54#
發(fā)表于 2025-3-30 22:32:06 | 只看該作者
55#
發(fā)表于 2025-3-31 04:03:10 | 只看該作者
The Methods and Applications of Monte Carlo in Low Energy (? 20 MeV) Neutron-Photon Transport (MORSE The discrete ordinate solution usually provides a rather complete description of the particle fluxes in all of phase space (spatial coordinates, x, y, z; angular direction, u., v., w.; time, t; energy, E; etc.) in contrast to the Monte Carlo solution which usually only provides information about ce
56#
發(fā)表于 2025-3-31 07:31:35 | 只看該作者
The Methods and Applications of Monte Carlo in Low Energy (? 20 MeV) Neutron-Photon Transport (MORSE.. Some of these are:l) fusion reactor shielding., 2) accelerator breeder design. (electronuclear fuel production), 3) high energy nuclear instrumentation design. (uranium calorimeters), and 4) accelerator beam stop activation.. In the sections to follow,1) and 2) will be discussed. The reader is re
57#
發(fā)表于 2025-3-31 11:25:57 | 只看該作者
Cross Section Processing Codes and Data Bases (AMPX)ing with ENDF-formatted nuclear data files or pseudo-problem-independent multigroup cross-section data, the system includes a full range of features needed to produce problem-dependent neutron, gamma-ray production, and gamma-ray interaction cross-section data for use with neutronics transport codes
58#
發(fā)表于 2025-3-31 13:55:41 | 只看該作者
59#
發(fā)表于 2025-3-31 17:46:42 | 只看該作者
60#
發(fā)表于 2025-3-31 23:04:26 | 只看該作者
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