coupled simulation of gas cooled fast reactor fuel assembly with nestle code system

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ID: 174312
2018
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Abstract
The paper is focused on coupled calculation of the Gas Cooled Fast Reactor. The proper modelling of coupled neutronics and thermal-hydraulics is the corner stone for future safety assessment of the control and emergency systems. Nowadays, the system and channel thermal-hydraulic codes are accepted by the national regulatory authorities in European Union for license purposes, therefore the code NESTLE was used for the simulation. The NESTLE code is a coupled multigroup neutron diffusion code with thermal-hydraulic sub-channel code. In the paper, the validation of NESTLE code 5.2.1 installation is presented. The processing of fuel assembly homogeneous parametric cross-section library for NESTLE code simulation is made by the sequence TRITON of SCALE code package system. The simulated case in the NESTLE code is one fuel assembly of GFR2400 concept with reflective boundary condition in radial direction and zero flux boundary condition in axial direction. The results of coupled calculation are presented and are consistent with the GFR2400 study of the GoFastR project.
Reference Key
osusky2018actacoupled Use this key to autocite in the manuscript while using SciMatic Manuscript Manager or Thesis Manager
Authors ;Filip Osusky;Stefan Cerba;Jakub Luley;Branislav Vrban;Jan Hascik
Journal BMC Bioinformatics
Year 2018
DOI
10.14311/APP.2018.14.0034
URL
https://ojs.cvut.cz/ojs/index.php/APP/article/view/4843
Keywords
civil engineering (general)

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