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首页> 美国政府科技报告 >Automated MCNP Photon Source Generation for Arbitrary Configurations of Radioactive Materials and First-Principles Calculations of Photon Detector Responses
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Automated MCNP Photon Source Generation for Arbitrary Configurations of Radioactive Materials and First-Principles Calculations of Photon Detector Responses

机译：用于任意放射性材料配置的自动mCNp光子源生成和光子探测器响应的第一原理计算

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A patch to the Los Alamos Monte Carlo code MCNP has been developed that automates the generation of source descriptions for photons from arbitrary mixtures and configurations of radioactive isotopes. Photon branching ratios for decay processes are obtained from national and international data bases and accesed directly from computer files. Code user input is generally confined to readily available information such as density, isotopic weight fractions, atomic numbers, etc. of isotopes and material compositions. The availbility of this capability in conjunction with the ''generalized source'' capability of MCNP Version 3A makes possible the rapid and accurate description of photon sources from complex mixtures and configurations of radioactive materials, resulting in improved radiation transport predictive capabilities. This capability is combined with a first - principles calculation of photon spectrometer response - functions for NaI, BGO, and HPGe for E sub gamma approx = or < 1 MeV. 25 refs., 1 fig., 4 tabs. (ERA citation 13:031618)

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