The SCALE code system's ability to address stochastic distributions of fuel particles within a
graphite matrix has been revisited in both multigroup (MG) features and continuous-energy …

Advanced reactor concepts currently being developed throughout the industry are
significantly different from light water reactor (LWR) designs with respect to geometry …

In the spring and summer of 2019, experiments were conducted at the High Temperature
Test Facility (HTTF) that form the basis of an upcoming high-temperature gas-cooled reactor …

Abstract The Very High Temperature Critical Assembly (VHTRC) experiment represents one
of the few data sets available for the validation of HTGR lattice physics. Within the framework …

The quantification of uncertainties in design and safety analysis of reactors is today not only
broadly accepted, but in many cases became the preferred way to replace traditional …

This article investigates a high temperature prismatic core small modular reactor concept
based on the U-Battery. To achieve a long operational time without reloading of the fuel, a …

Key problems in the simulation of pebble-bed high-temperature gas-cooled reactors include
approximations of TRISO fuel particles and pebble-bed models, choice of nuclear data …

As one of the Generation-IV advanced reactor types, High Temperature Gas-Cooled
Reactors (HTGRs) can provide high-quality heat to industrial processes, in addition to …

This work is focused on the improvement of the graphite impurity content characterization for
the ASTRA critical facility. The equivalent boron content for the graphite reflectors of the …

The SCALE code system was used to model, deplete, and compare several different tri-
structural isotropic (TRISO)–fueled reactor designs: a helium-cooled prismatic reactor, a …