https://doi.org/10.1051/epjconf/202328804010
Flux and Nuclear Heating Rate Calculations for CALORRE Irradiation in MITR
1 Massachusetts Institute of Technology, Nuclear Reactor Laboratory, Cambridge, Massachusetts, USA
2 Aix Marseille Univ, Université de Toulon, CNRS, IM2NP, Marseille, France
3 CEA/DES/IRESNE/DER, Section of Experimental Physics, Safety Tests and Instrumentation, Cadarache, F-13108, Saint Paul-lez-Durance, France
Published online: 21 November 2023
This work summarizes neutronic calculations performed for the CALORRE differential calorimeter specifically designed by Aix Marseille University to inform the irradiation campaign planning for testing in MITR within the framework of the CALOR-I research program. MCNP software was used to predict the neutron and gamma flux spectrum, and total nuclear heating rate to the components of the calorimeter in a variety of positions. Results were compared to evaluate spatial bias, core loading effects, optimization for axial position, and provide input data for thermal multi-physics modelling.
Key words: Calorimeter / Nuclear Heating Rate / Neutronics
© The Authors, published by EDP Sciences, 2023
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
