A Neutronic Program for Critical and Nonequilibrium Study of Mobile Fuel Reactors: The Cinsf1D Code

Small Modular Reactors: An Overview of Modeling, Control, Simulation, and Applications

“…As the point dynamic model is developed, multidimensional neutronic dynamic models were proposed to improve the accuracy and efficiency of transient simulations. In 2003, [101] introduced a 1D dynamic model for calculating steady-state status and analyzing accidental transients. In 2006, [102] developed a 2D dynamic model utilizing discretized time-spatial dependent equations to study transient characteristics.…”

Development and application of a system analysis code for liquid fueled molten salt reactors based on RELAP5 code

“…Ball and Kerlin (1965) modified the calculation process of the DNPs by accounting for the decay outside the core. Lecarpentier and Carpentier (2003) solved one-dimensional two-energy-group neutron diffusion equations by adding convective term in DNP equations. Lapenta et al (2001) deduced the point kinetic model for fluid fueled systems through diffusion equations by inclusion of a convective term in the delayed neutrons balance equations and the introduction of unconventional boundary conditions.…”

“…Many efforts focused on analyzing the safety feature and optimization of the liquid fueled MSRs have been carried out by different authors and organizations with different simplifying hypothetical models. Lecarpentier and Carpentier (2003) developed the Cinsf1D code in one-dimension geometry using two-energy-group diffusion and a spatial dimension neutronic model. Krepel et al (2005Krepel et al ( , 2007 extended the DYN1D/DYN3D code for molten salt reactors, in which the neutron diffusion equations were employed for neutrons calculation.…”

A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics

“…Efforts in the development of suitable simulation tools were made by different authors and for a variety of molten salt systems (Mylonakis et al, 2014), but most of the studies carried out are featured by various simplifying hypotheses, such as assuming known velocities (Lapenta et al, 2001;Dulla et al, 2004;Dulla and Ravetto, 2007), one-dimensional flow and simplified heat transfer models (Lecarpentier and Carpentier, 2003;Yamamoto et al, 2005Yamamoto et al, , 2006Krepel et al, 2014aKrepel et al, , 2005Krepel et al, , 2007Shimazu, 2006, 2008;K oph azi et al, 2009;Zhang et al, 2009a,c), simple crosssection feedback (Nicolino et al, 2008), only steady-state conditions (Wang et al, 2006;Zhang et al, 2009b). Recently, coupled approaches have been developed for the modelling of neutronics, heat transfer and fluid-dynamics, either by coupling a multiplechannel thermal-hydraulic analysis code with a Monte Carlo neutronic code (Guo et al, 2013) or by solving directly the governing equations in a multi-dimensional domain (Nagy et al, 2014;Zhang et al, 2014).…”