Characterization of the TRIGA Mark II reactor full-power steady state

被引:17
作者
Cammi, Antonio [1 ]
Zanetti, Matteo [1 ]
Chiesa, Davide [2 ,3 ]
Clemenza, Massimiliano [2 ,3 ]
Pozzi, Stefano [2 ,3 ]
Previtali, Ezio [2 ,3 ]
Sisti, Monica [2 ,3 ]
Magrotti, Giovanni [4 ]
Prata, Michele [4 ]
Salvini, Andrea [4 ]
机构
[1] Politecn Milan, Dept Energy, CeSNEF Enrico Fermi Ctr Nucl Studies, Via La Masa 34, I-20156 Milan, Italy
[2] Univ Milano Bicocca, Phys Dept G Occhialini, Piazza Ateneo Nuovo, I-20126 Milan, Italy
[3] Univ Milano Bicocca, INFN Sect, Piazza Ateneo Nuovo, I-20126 Milan, Italy
[4] Univ Pavia, Appl Nucl Energy Lab LENA, Via Gaspare Aselli 41, I-27100 Pavia, Italy
关键词
NEUTRON; SIMULATION; UNIVERSITY;
D O I
10.1016/j.nucengdes.2016.01.026
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In this paper, the characterization of the full-power steady state of the TRIGA Mark II nuclear reactor at the University of Pavia is achieved by coupling the Monte Carlo (MC) simulation for neutronics with the "Multiphysics" model for thermal-hydraulics. Neutronic analyses have been carried out with a MCNP5 based MC model of the entire reactor system, already validated in fresh fuel and zero-power configurations (in which thermal effects are negligible) and using all available experimental data as a benchmark. In order to describe the full-power reactor configuration, the temperature distribution in the core must be established. To evaluate this, a thermal-hydraulic model has been developed, using the power distribution results from the MC simulation as input. The thermal-hydraulic model is focused on the core active region and takes into account sub-cooled boiling effects present at full reactor power. The obtained temperature distribution is then entered into the MC model and a benchmark analysis is carried out to validate the model in fresh fuel and full-power configurations. An acceptable correspondence between experimental data and simulation results concerning full power reactor criticality proves the reliability of the adopted methodology of analysis, both from the perspective of neutronics and thermal-hydraulics. (C) 2016 Elsevier B.V. All rights reserved.
引用
收藏
页码:308 / 321
页数:14
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