Introduction to Moltres: An application for simulation of Molten Salt Reactors

Functional Requirements for the Modeling and Simulation of Advanced (Non-LWR) Reactor Mechanistic Source Term

“…Other efforts have also completed safety assessments using methodologies published from IAEA's International Project on Innovative Nuclear Power Reactor and Fuel Cycles (INPRO) [30]. Published safety analyses of MSRs using an assortment of nuclear codes, often coupled with thermal hydraulic codes, are available in refs [31][32][33][34][35][36][37][38][39]. Some of these efforts have shown that source term functionality can be added to these codes by tracking specific fission product isotopes with the flow [40][41][42][43].…”

The MOOSE Electromagnetics Module

“…The MOOSE project was started to support the modeling and simulation needs of the nuclear energy and fuels community [4,6], but has since developed capability in plasma liquid interactions [7], molten salt reactors [8], geochemistry [9], and sintering [10], amongst many other technical areas. However, the wider MOOSE ecosystem was unable to take easy advantage of CEM models and methods which were native to the framework and also directly couplable to established MOOSEbased codes.…”

Safety Analysis of Molten Salt Fast Reactor Fuel Composition using Moltres

“…As mentioned in the previous Moltres study [1], the neutronics in Moltres is described by the time-independent multigroup neutron diffusion equation as shown in Equation 1:…”

“…New MSR simulation tools must capture strong coupling between neutronics and thermal-hydraulics exhibited by delayed neutron precursor (DNP) movement as well as strong Doppler and density feedback in the fuel salt. This paper investigates the impact of changing fuel composition on fuel salt temperatures in the Molten Salt Fast Reactor (MSFR) concept using a new simulation tool for MSRs, Moltres [1].…”