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Demonstration of the coupled CORE SIM neutronic and thermo-hydraulic tool

Victor Dykin (Institutionen för teknisk fysik, Nukleär teknik) ; Christophe Demazière (Institutionen för teknisk fysik, Nukleär teknik)
Göteborg : Chalmers University of Technology, 2014. - 26 s.
[Rapport]

This report deals with the demonstration of an innovative coupled neutronic/themo-hydraulic tool, for which the models and algorithms were already presented in a companion report. The novelty of the tool resides in its versatility, since many different systems can be investigated and different kinds of calculations can be performed. More precisely, both critical systems and subcritical systems with an external neutron source can be studied, and static and dynamic cases in the frequency domain (i.e. for stationary fluctuations) can be considered. For each situation, the three-dimensional distributions of the static neutron fluxes, all thermo-hydraulic parameters, their respective first-order noise are estimated, as well as the effective multiplication factor of the system. The main advantages of the tool, which is entirely MATLAB based, lie with the robustness of the implemented numerical algorithms, its high portability between different computer platforms and operative systems, and finally its ease of use since no input deck writing is required. The present version of the tool, which is based on two-group diffusion theory, is mostly suited to investigate thermal systems, both Pressurized and Boiling Water Reactors (PWR and BWR, respectively). The tool, for which a complete user’s manual exists, is freely available on direct request to the authors of the present report.

Nyckelord: core simulator, coupled neutronics/thermal-hydraulics, noise analysis



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Denna post skapades 2014-10-09. Senast ändrad 2015-03-30.
CPL Pubid: 204034

 

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Institutioner (Chalmers)

Institutionen för teknisk fysik, Nukleär teknik (2006-2015)

Ämnesområden

Energi
Beräkningsfysik
Teknisk fysik

Chalmers infrastruktur

Ingår i serie

CTH-NT - Chalmers University of Technology, Nuclear Engineering 301