This paper presents a novel reduced-order model (ROM) based data assimilation framework
for parametric high-fidelity time-dependent neutron transport equations (TNTE). The ROM is …

The stiffness confinement method (SCM) is implemented in the variational nodal method
(VNM) framework to solve time-dependent multi-group neutron transport equations. With …

This article describes the transient models of the neutronics code VITAS that are used for
solving time-dependent, pin-resolved neutron transport equations. VITAS uses the stiffness …

Modeling the time-dependent transient behavior of nuclear reactors with high-fidelity pin-
resolved detail has increased importance when the operating power of the reactor is …

Abstract The 3D Method of Characteristics (MOC) has high numerical accuracy, geometrical
flexibility, making it suitable for the simulation of advanced reactors with complex geometry …

In this paper, an integrated code is proposed to simulate the transient thermo-neutronic
behavior of the Xi'an Pulsed Reactor (XAPR) core during reactivity insertion accidents (RIA) …

This work presents a new formulation of the axial expansion transport method explicitly
using Legendre polynomials for arbitrarily high-order expansions. This new formulation also …

The heterogeneous variational nodal method (HVNM) has emerged as a potential approach
for solving high-fidelity neutron transport problems. However, achieving accurate results with …

In this report, we document the investigations of feedback models for the passive control
systems being designed as a part of this NEUP project. This work builds on our previous …

In order to meet the growing worldwide electricity demand while reducing the environmental
impacts from CO2-emission energy sources, the next-generation nuclear reactor systems …