One major accident of interest in the High Temperature Gas-Cooled Reactors is the Pressurized Conduction Cooldown (PCC) scenario. The PCC scenario results in a loss of forced convection to the core, while the loop stays pressurized since there is no breach in the boundary. The coolant flows through … [Read more...]
V&V Benchmark Problem #2 – Single-Jet Computational Fluid Dynamics (CFD) Numeric Model Validation
The ASME V&V 30 Subcommittee on Verification and Validation in Computational Nuclear System Thermal Fluids Behavior is supporting a series of verification and validation (V&V) benchmark problems designed to study the scope and key ingredients of the V&V 30 Subcommittee's charter. This … [Read more...]
The Water-Cooled Reactor Cavity Cooling System (RCCS)
The Very High Temperature Gas-Cooled Reactor (VHTR) is one of the six Gen IV reactor designs, which will generate electricity and high temperature heat for industrial applications. The design of the VHTR includes a new passive safety system that is designed to remove heat and maintain temperatures … [Read more...]
Pebble Bed Test Facility
The Advanced High-Temperature Reactor (AHTR) concept leverages a particle-based fuel format consisting of discrete spherical graphite pebbles arrayed in a packed bed architecture. Thermal regulation achieved via flow of gas (e.g., helium) or liquid (e.g., molten salt) coolants through the void … [Read more...]
Evaluation and Testing of HTGR Reactor Building Response to Depressurization Accidents
The analysis and understanding of air ingress events are an important aspect of the design of high-temperature gas-cooled reactor (HTGR). During accident conditions (depressurized loss of forced cooling, D-LOFC) air may enter into the reactor pressure vessel as a result of a break in the helium … [Read more...]
