NEUTRONIC MODELING OF MOLTEN SALT REACTORS


41th Annual CNS-CNA Student Conference - 2017 June 05

Presented at:
41th Annual CNS-CNA Student Conference
2017 June 05
Location:
Niagara Falls, ON Canada
Session Title:
Student Posters, Wine-&-Cheese Reception

Authors:
U. Shahid (McMaster University)
M.A. Allaf (Istanbul Technical University)
F.O. Ozkan (Istanbul Technical University)
A. Yilmazer (Hacettepe University)
  

Abstract

The main objective of this study is to obtain an analytical solution to multi-group diffusion equations of MSRs. As a starting point, one group criticality calculations including delayed neutrons are carried out both for no-recirculation and recirculation cases, respectively. The effect of fuel’s velocity and recirculation loop length on the criticality of the system as well as the difference between recirculation and non-recirculation systems on the delayed neutron precursors is investigated. Then, neutronic modeling has been done for FUJI-233Um (450 MWth) MSR using MCNP-IV. The analytical solution employed in the one-group diffusion theory of MSR is extended to the multi-group case.

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