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 manner using standalone neutronics calculations, without the inclusion of thermal distributions. We utilize the Multiphysics Object-Oriented Simulation Environment (MOOSE) framework — in particular Griffin and Pronghorn — for generating global and local neutron kinetics parameters which includes the use of thermal fluid distributions to account for localized effects. This work establishes a methodology for calculating the reactor kinetics parameters for a pebble bed high-temperature gas reactor using Griffin and Pronghorn for a coupled neutronics/thermal fluids analysis to provide high fidelity point kinetics data. Neutron kinetics parameters generated on a global and local basis are compared against a full diffusion solve for a typical load-following transient. Locally-generated neutron kinetic parameters are able to reduce the maximum error in the transient power level from 5\% to below 1.5\%; along with this, bulk temperature errors were reduced from 12 K to 4 K.
