Most of the existing nuclear power plants (NPPs) in the world rely on traditional analog
instrumentation and control (I&C) systems for monitoring, control, and protection functions …

The focus of this report is to present an integrated research and development roadmap to
identify and perform high-value evaluations of advanced nuclear technology concepts with …

This report provides a status of development of utility RISA Use Case applications for which
potential sponsoring utility partners have been identified. These applications were …

Abstract The LOCA Toolkit for US light water reactors (LOTUS) currently under development
at Idaho National Labs (INL) is a plug and play, multiphysics environment to be used in …

The nuclear industry and the US Department of Energy are jointly develo** accident
tolerant fuel (ATF) which has the potential to greatly improve the safety and economic …

ABSTRACT A methodology using multiple fuel rods modeling scheme pursuant to the
system thermalhydraulic calculation representing the various fuel rods of different burnup …

Abstract A Risk-informed Safety Margin Characterization (RISMC) analysis method based
on RAVEN software and Monte Carlo (MC) sampling is introduced in the paper. The …

Extending the fuel discharge burnup level, eg, from the current limit of rod averaged
discharge burnup limit of 62 GWD/MT to a proposed new limit of 75 GWD/MT, can provide …

Since the revision of the requirements to consider the effect of fuel burnup on emergency
core cooling system performance was proposed, flow blockage in reactor core has been one …

An approach to uncertainty quantification and sensitivity analysis with coupled simulations of
VERACS/FRAPCON and VERA-CS/BISON was developed within the Multi-Physics Best …