Improved computer capabilities and parallel algorithms have enabled high fidelity coupled
analyses of classical nuclear power plant designs, which can also be applied to analyze the …

The aim of this contribution is to deeply introduce the ALCYONE Fuel Performance Code.
ALCYONE is being implemented within the PLEIADES numerical framework and is …

Nuclear fuel performance analysis is fundamental for the design of pressurized water
reactors (PWRs) with great safety concerns. The analysis of a fuel rod involves many …

The paper describes the development, validation, and use of UWB 1 code intended for fast
calculation of nuclear fuel depletion in burnable absorber research. The degree of …

The nuclear reactor is a multi-physics and multiscale coupling system. The conditions of
high temperature and high neutron flux in the reactor pose a significant challenge to the …

To accurately assess the in-pile performance of the accident tolerant fuel (ATF) over the
whole life for the light water reactors (LWR), a full coupling of neutronics/thermal …

This report summarizes key aspects of research in evaluation of modeling needs for TREAT
transient simulation. Using a measured TREAT critical measurement and a transient for a …

This paper provides a detailed description of the Godiva benchmark problem suitable for
multiphysics code verification. Multigroup transport weak forms for general curvilinear …

A new task of using the Jacobian-Free-Newton-Krylov (JFNK) method for the PWR core
transient simulations involving neutronics, thermal hydraulics and mechanics is conducted …

To further the development of low-enriched uranium fuels, precedence has been placed on
delivering the same amount of power while lowering the fuel temperature and radial …