ABSTRACT
This article offers a general description of how nuclear data (cross sections, spectra of emitted particles, radioactive decay data, etc.) is organized and processed for use by software dedicated to nuclear applications, solving both the neutron and gamma ray transport equation (Boltzman equation) and the nuclide generation/depletion generalized coupled Bateman equations. Given the central role of neutrons in nuclear reactor physics, their cross sections are given special emphasis in this article.
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INTRODUCTION
The articles Reactor physics – The basics of nuclear physics
[BN 3 010]
and Reactor physics – Nuclear reactions
[BN 3 011]
present the main characteristics of the atomic nucleus and of the nuclear phenomena of radioactivity and nuclear reactions. These characteristics are represented by sets of numerical values, which specialists refer to as basic physical data, nuclear data, atomic data and spectroscopic data. The term "nuclear data" is sometimes used generically to cover all these data.
This article outlines the way in which nuclear data (cross sections, particle emission spectra, radioactive decay data, etc.) are organized, physically and numerically processed for use, in particular, by software dedicated to nuclear applications, solving on the one hand the transport equation (Boltzmann equation) for neutrons and gamma rays in matter, and on the other hand the equations for the temporal evolution of nuclide concentrations (generalized Bateman equations). The central importance of neutrons in nuclear reactor physics justifies the special place given to them in this article.
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KEYWORDS
dosimetry
| neutronics
| ENDF format
| pointwise cross section
| generalized Bateman coupled equations
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Nuclear Reactor Physics - Nuclear Data Processing