A novel core analysis method for prismatic high temperature gas reactors
Huning, Alexander Jared
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A new transient thermal hydraulic method for simulating prismatic HTGRs during a loss-of-forced-circulation (LOFC) accident is presented. This expands upon the steady state thermal hydraulic methodology presented in the Author’s MS Thesis. However, several key additions have been made. The largest is the addition of a transient analysis method that computes the fluid mass, velocity (momentum), and energy throughout a transient. This is achieved by using a well-documented, semi-implicit pressure-correction scheme. The fluid volumes are assumed to be 1-D to allow for the use of standard heat transfer and pressure drop correlations. Simple transient velocity and pressure boundary conditions are employed. Helium is assumed to be an ideal gas with constant specific heats, which allows for the use of simple thermodynamic relationships to close the fluid model. Models for reactor containment cooling (RCCS) heat transfer and decay heat generation have also been added. Using the method developed here, both the pressurized (P-LOFC) and de-pressurized (D-LOFC) accident have been simulated. Results from these analyses confirm the HTGR’s key safety advantage over all LWRs and most other advanced reactor designs, which is to have passive, indefinite cooling capability for the most limiting accident.