COUPLED SIMULATION OF GAS COOLED FAST REACTOR FUEL ASSEMBLY WITH NESTLE CODE SYSTEM

Filip Osusky; Stefan Cerba; Jakub Luley; Branislav Vrban; Jan Hascik

doi:10.14311/APP.2018.14.0034

Acta Polytechnica CTU Proceedings (May 2018)

COUPLED SIMULATION OF GAS COOLED FAST REACTOR FUEL ASSEMBLY WITH NESTLE CODE SYSTEM

Filip Osusky,
Stefan Cerba,
Jakub Luley,
Branislav Vrban,
Jan Hascik

Affiliations

Filip Osusky: Institute of Nuclear and Physical Engineering, Faculty of Electrical Engineering and Information Technology, Slovak University of Technology in Bratislava, Ilkovicova 3, Bratislava, Slovakia
Stefan Cerba: Institute of Nuclear and Physical Engineering, Faculty of Electrical Engineering and Information Technology, Slovak University of Technology in Bratislava, Ilkovicova 3, Bratislava, Slovakia
Jakub Luley: Institute of Nuclear and Physical Engineering, Faculty of Electrical Engineering and Information Technology, Slovak University of Technology in Bratislava, Ilkovicova 3, Bratislava, Slovakia
Branislav Vrban: Institute of Nuclear and Physical Engineering, Faculty of Electrical Engineering and Information Technology, Slovak University of Technology in Bratislava, Ilkovicova 3, Bratislava, Slovakia
Jan Hascik: Institute of Nuclear and Physical Engineering, Faculty of Electrical Engineering and Information Technology, Slovak University of Technology in Bratislava, Ilkovicova 3, Bratislava, Slovakia

DOI: https://doi.org/10.14311/APP.2018.14.0034
Journal volume & issue: Vol. 14, no. 0
pp. 34 – 41

Abstract

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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.

coupled calculation, fast reactor, GFR 2400, NESTLE, neutronics, thermal-hydraulics, thermal feedback, validation

Published in Acta Polytechnica CTU Proceedings

ISSN: 2336-5382 (Online)
Publisher: CTU Central Library
Country of publisher: Czechia
LCC subjects: Technology: Engineering (General). Civil engineering (General)
Website: https://ojs.cvut.cz/ojs/index.php/APP

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