کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1727834 1521099 2016 7 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Optimising differential data formats for Monte-Carlo radiation transport in the fusion regime
ترجمه فارسی عنوان
بهینه سازی فرمت های داده های دیفرانسیل برای انتقال تابش مونت کارلو در رژیم همجوشی
کلمات کلیدی
پیش پردازش داده های هسته ای؛ MCNP؛ سوخت هسته ای
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
چکیده انگلیسی

Monte-Carlo based radiation transport codes are widely used to simulate the behaviour of nuclear facilities, to aid their design, operation and inform on safety aspects. The accuracy, and hence reliability, of the output of transport codes is entirely dependent on the underlying nuclear data. The formalism used in the processed data directly impacts on the computational performance for such calculations. For example, low data density results in faster computation possibly made at the expense of accuracy and vice versa. A current standard transport code, MCNP, requires pre-processing and reformatting of raw nuclear data files (ENDF) before their use within the simulation. The incident particles angular distribution is usually processed to an equal probability histogram with 32 channels, or to a set of data points with linear interpolation across the angular and energy range. The former method is fast to sample, yet sacrifices the accuracy of the data representation. The latter method provides a better representation of the original format, but has a tendency to produce larger data files that are correspondingly slower to sample. This study considers the relative accuracies of these processing formalisms and the relationship to computational efficiency via an in-house, simplified Monte-Carlo code. For future code developments within the fusion community, we consider variations upon both methods in an effort to determine the optimal balance between computational efficiency and accurate data representation. We also attempt to quantify the effects of a lesser accuracy versus high computational burden in the simulation of fusion reactor design.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 98, December 2016, Pages 36–42
نویسندگان
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