Processing of Thermal-hydraulic Approximations in the GFR 2400 Fast Reactor Design

被引：0
|
作者：
Osusky, Filip [1 ]
Vrban, Branislav [1 ]
Cerba, Stefan [1 ]
Luley, Jakub [1 ]
Necas, Vladimir [1 ]
机构：
[1] Slovak Univ Technol Bratislava, Fac Elect Engn & Informat Technol, Inst Nucl & Phys Engn, Ilkovicova 3, Bratislava 81219, Slovakia
来源：
29TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2020) | 2020年
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中图分类号：
X [环境科学、安全科学];
学科分类号：
08 ; 0830 ;
摘要：
The paper investigates the influence of the used thermal-hydraulic approximations in the coupled calculations of Gas-cooled Fast Reactor design (hereby GFR 2400). The NESTLE code is used as coupled simulation tool and solves multigroup neutron diffusion equation by finite difference method that is internally coupled with thermal-hydraulic sub-channel code. The inhouse developed code referred as TENPIN is used to prepare the thermal-hydraulic data for GFR 2400 design. The TENPIN code solves steady state heat balance equation with flowing coolant in triangular lattice cell together with temperature dependent thermal-hydraulic properties of the fuel, cladding and coolant. Based on calculated fuel bundle temperature distributions by the TENPIN code, the thermal-hydraulic approximations suitable for the NESTLE code are processed. The results of the analyses are compared with the previous study utilizing the FLUENT code (from ANSYS code package system) for processing of thermal-hydraulic approximations. Changes in neutronic and thermal-hydraulic distributions are described and visualized in the paper.
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页数：9
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