Specifications for a coupled neutronics thermal-hydraulics SFR test case

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

Tassone, A.^1 ; Smirnov, A.D.^2 ; Tikhomirov, G.V.^2

Department of Astronautical, Electrical and Energy Engineering Nuclear Section, Sapienza Universit di Roma, Corso Vittorio Emanuele II 244, Roma

00186, Italy^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: Axial distribution;    Material compositions;    Scientific community;    Separate analysis;    Sodium cooled fast reactors (SFR);    Thermal hydraulics;    Thermo-physical property;    Volumetric power;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/781/1/012047/pdf
DOI  :  10.1088/1742-6596/781/1/012047

来源: IOP

【 摘 要 】

Coupling neutronics/thermal-hydraulics calculations for the design of nuclear reactors are a growing trend in the scientific community. This approach allows to properly represent the mutual feedbacks between the neutronic distribution and the thermal-hydraulics properties of the materials composing the reactor, details which are often lost when separate analysis are performed. In this work, a test case for a generation IV sodium-cooled fast reactor (SFR), based on the ASTRID concept developed by CEA, is proposed. Two sub-assemblies (SA) characterized by different fuel enrichment and layout are considered. Specifications for the test case are provided including geometrical data, material compositions, thermo-physical properties and coupling scheme details. Serpent and ANSYS-CFX are used as reference in the description of suitable inputs for the performing of the benchmark, but the use of other code combinations for the purpose of validation of the results is encouraged. The expected outcome of the test case are the axial distribution of volumetric power generation term (q), density and temperature for the fuel, the cladding and the coolant.