Methods for solving the time-dependent neutron diffusion equation for nuclear reactor
analysis are discussed. Techniques for treating the spatial variables, as well as techniques …

We have applied the black-box paradigm to assembly homogenization and introduced
current discontinuity factors (CDFs) for an arbitrary low-order operator in the presence of …

Monte Carlo neutron transport codes are widely used in various reactor physics
applications, traditionally related to criticality safety analyses, radiation shielding problems …

This paper describes the methods used in the Serpent 2 Monte Carlo code for producing
homogenized group constants for nodal diffusion and other deterministic reactor simulator …

A new nodal method that directly solves the multidimensional diffusion equation without the
transverse integration procedure is described. The new method expands the homogeneous …

Advanced manufacturing has the potential to revitalize US manufacturing, with valuable
applications in several industries, including aerospace, automotive, and construction. Some …

As a key and core knowledge for the design of various types of nuclear reactors, the
discipline of reactor physics has been advanced continually in the past six decades and has …

The Serpent-ARES code sequence, applying Monte Carlo based group constants in a full-
core nodal diffusion calculation, is currently being validated for PWR fuel cycle simulations …

PWR-core fuel management calculation code system named NECP-Bamboo is designed to
meet different requirements from engineering application, scientific research and nuclear …

Traditional light water reactor simulations are usually either high fidelity, requiring hundreds
of node-hours, or low fidelity, requiring only seconds to run on a common workstation. In …