Multi-physics numerical analysis of the fuel-addition transients in the liquid-fuel molten salt reactor

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].…”

Survey and Assessment of Computational Capabilities for Advanced (Non-LWR) Reactor Mechanistic Source Term Analysis.

“…Similarly, Wan et al also developed an in-house multi-physics solver to model the MSFR during steady-state and transients, providing spatial and time distributions of various parameters [170]. Specifically, they simulate the effect of both fissile and fertile fuel additions to the reactor, noting the evolution of power and core-averaged temperature during the transient.…”