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Neutronics Models for Integrated Testing of Transport NPP on Land-Based Prototype Testing Facilities.

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Title: Neutronics Models for Integrated Testing of Transport NPP on Land-Based Prototype Testing Facilities.
Authors: Artemov, V. G.1 otd10@mail.ru, Artemova, L. M.1, Bessonov, D. Yu.1, Zinatullin, R. E.1, Ivanov, A. S.1, Karpov, A. S.1, Korotaev, V. G.1, Kuznetsov, A. N.1, Piskarev, A. V.1
Source: Atomic Energy. Jun2022, Vol. 132 Issue 2, p75-81. 7p.
Subjects: Testing laboratories, Software development tools, Prototypes, Integrated software, Systems software
Abstract: An approach to providing computational support for tests of TNPPs on prototype stands using software tools for the integrated modeling of neutronics and thermohydraulic processes is presented. The basic software systems and models developed on their basis for calculating per-fuel-rod characteristics of fuel assemblies in quasi-static (burnup calculation) and dynamic regimes, as well as for conducting computational experiments using uncertainty and sensitivity analysis method, are considered. [ABSTRACT FROM AUTHOR]
Copyright of Atomic Energy is the property of Springer Nature and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
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  Data: <searchLink fieldCode="JN" term="%22Atomic+Energy%22">Atomic Energy</searchLink>. Jun2022, Vol. 132 Issue 2, p75-81. 7p.
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  Data: An approach to providing computational support for tests of TNPPs on prototype stands using software tools for the integrated modeling of neutronics and thermohydraulic processes is presented. The basic software systems and models developed on their basis for calculating per-fuel-rod characteristics of fuel assemblies in quasi-static (burnup calculation) and dynamic regimes, as well as for conducting computational experiments using uncertainty and sensitivity analysis method, are considered. [ABSTRACT FROM AUTHOR]
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  Data: <i>Copyright of Atomic Energy is the property of Springer Nature and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
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