Demonstrate Capability of NEAMS Tools to Generate Reactor Kinetics Parameters for Pebble Bed HTGRs Transient Modeling
The system analysis of anticipated operating occurrences and design basis accident for pebblebed reactor systems requires knowledge of the neutron kinetic parameters. These parameters take into account various types of feedback from the pebble-bed core and are typically integrated into system analysis tools such as the System Analysis Module (SAM) in the Nuclear Energy Advanced […]
HI-STORM Overpack and MPC-32 Thermal-Hydraulic Model with MOOSE Framework
Nuclear power is a significant source of electricity in the United States, but the average age of nuclear power plants is around 40 years old. The safe management of the spent nuclear fuel (SNF) is a key aspect of the back-end of the nuclear fuel cycle. Spent fuel dry storage systems are becoming a popular […]
The Virtual Test Bed (VTB) Repository: A Library of Reference Reactor Models Using NEAMS Tools
With the next generation of nuclear reactors under development, modeling and simulation tools are being developed by the U.S. Department of Energy to support their design, licensing, and future operation. Mirroring the physical test beds currently under construction (i.e., Demonstration and Operation of Microreactor Experiments, known as DOME, and Laboratory for Operating and Testing in […]
Discrete element simulation of Pebble Bed Reactors on graphics processing units
Prediction of pebble positions in a Pebble Bed Reactor (PBR) is necessary for both reactor physics and thermal hydraulics simulations as the arrangement of pebbles has a significant impact on the resulting core power, coolant flow, and fuel temperature. Knowledge of pebble movement as the fuel is cycled through the core is also critical for […]
Develop MOOSE thermalmodel of MPC-32 canister and HI-STORM overpack
Nuclear power is a significant source of electricity in the United States, but the average age of nuclear power plants is around 40 years old. The safe management of the spent nuclear fuel (SNF) is a key aspect of the back-end of the nuclear fuel cycle. Spent fuel dry storage systems are becoming a popular […]
Generation of localized reactor point kinetics parameters using coupled neutronic and thermal fluid models for pebble-bed reactor transient analysis
The systems analysis of anticipated operating occurrences and design basis accidents for pebble-bed reactor systems requires knowledge of neutron point kinetic parameters. These parameters take into account various types of feedback from the pebble-bed core and are typically integrated into systems analysis tools. Typically, the generation of neutron kinetics parameters is performed in a global […]