Test case specifications for coupled neutronics-thermal hydraulics calculation of Gas-cooled Fast Reactor

International Conference for Young Scientists, Specialists, and Postgraduates on Nuclear Reactor Physics 2016

Osuský, F.^1 ; Bahdanovich, R.^2 ; Farkas, G.^1 ; Haík, J.^1 ; Tikhomirov, G.V.^2

Institute of Nuclear and Physical Engineering, Faculty of Electrical Engineering and Information Technology, Slovak University of Technology in Bratislava, Ilkoviova 3, Bratislava

81219, Slovakia^1

Department of Theoretical and Experimental Physics of Nuclear Reactors, National Research Nuclear University, MEPhI (Moscow Engineering Physics Institute), Kashirskoe Shosse 31, Moscow

115409, Russia^2

关键词: Coupled calculation;    Gas cooled fast reactors;    Group representation;    Material compositions;    Numerical representation;    Operational conditions;    Test case specifications;    Thermal-hydraulics models;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/781/1/012038/pdf
DOI  :  10.1088/1742-6596/781/1/012038

来源: IOP

【 摘 要 】

The paper is focused on development of the coupled neutronics-thermal hydraulics model for the Gas-cooled Fast Reactor. It is necessary to carefully investigate coupled calculations of new concepts to avoid recriticality scenarios, as it is not possible to ensure sub-critical state for a fast reactor core under core disruptive accident conditions. Above mentioned calculations are also very suitable for development of new passive or inherent safety systems that can mitigate the occurrence of the recriticality scenarios. In the paper, the most promising fuel material compositions together with a geometry model are described for the Gas-cooled fast reactor. Seven fuel pin and fuel assembly geometry is proposed as a test case for coupled calculation with three different enrichments of fissile material in the form of Pu-UC. The reflective boundary condition is used in radial directions of the test case and vacuum boundary condition is used in axial directions. During these condition, the nuclear system is in super-critical state and to achieve a stable state (which is numerical representation of operational conditions) it is necessary to decrease the reactivity of the system. The iteration scheme is proposed, where SCALE code system is used for collapsing of a macroscopic cross-section into few group representation as input for coupled code NESTLE.