M. DeHart

发表

Reactor Physics Methods and Analysis Capabilities in SCALE

Stephen M. Bowman, Mark D. DeHart, S. Bowman, 2011 .

Integrated Keno v.a Monte Carlo transport for multidimensional depletion within scale

L. M. Petrie, Lester M Petrie, Mark D. DeHart, 2004 .

Multiphysics Simulation of Fuel Relocation for a Single Fuel Pin During Startup

F. Gleicher, M. DeHart, M. Lund, 2017 .

Burnable absorbers in nuclear reactors – A review

Jordan A. Evans, M. DeHart, D. D. Keiser, 2022, Nuclear Engineering and Design.

On the effects of pre- and post-transient rod positions for TREAT temperature-limited transient powers

M. DeHart, S. Goluoglu, 2018 .

Year End Progress Report on Rattlesnake Improvements

F. Gleicher, M. DeHart, Yaqi Wang, 2015 .

Coupled Multiphysics Simulations of Heat Pipe Microreactors Using DireWolf

R. Martineau, D. Andrs, C. Matthews, 2021, Nuclear Technology.

A new mathematical adjoint for the modified SAAF-SN equations

R. Martineau, M. DeHart, Yaqi Wang, 2015 .

Weighted delta-tracking in scattering media

M. DeHart, R. Slaybaugh, J. Rehak, 2018, Nuclear Engineering and Design.

Design and assessment of a molten chloride fast reactor

M. DeHart, S. Goluoglu, Zander Mausolff, 2021 .

Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages

Mark D. DeHart, M. DeHart, 1996 .

A discrete ordinates approximation to the neutron transport equation applied to generalized geometries

M. DeHart, Mark David Dehart, 1992 .

A Coupled Multiscale Approach to TREAT LEU Feedback Modeling Using a Binary-Collision Monte-Carlo–Informed Heat Source

Javier Ortensi, Mark DeHart, Daniel Schwen, 2018, Nuclear Science and Engineering.

Interpretation of energy deposition data from historical operation of the transient test facility (TREAT)

Javier Ortensi, Mark DeHart, Benjamin Baker, 2017 .

Weighted Delta-Tracking with Scattering

M. DeHart, R. Slaybaugh, J. Rehak, 2018 .

An Extension of the Validation of SCALE (SAS2H) Isotopic Predictions for PWR Spent Fuel

DeHart, O. W. Hermann, M. DeHart, 1996 .

Inter-Disciplinary Collaboration in Support of the Post-Standby TREAT Mission

John D. Bess, Javier Ortensi, Mark DeHart, 2016 .

EVALUATION OF CORE PHYSICS ANALYSIS METHODS FOR CONVERSION OF THE INL ADVANCED TEST REACTOR TO LOW- ENRICHMENT FUEL

Mark D. DeHart, Gray S. Chang, M. DeHart, 2012 .

An extended step characteristic method for solving the transport equation in general geometries

Theodore A. Parish, Mark D. DeHart, M. DeHart, 1994 .

Hybrid super homogenization and discontinuity factor method for continuous finite element diffusion

Richard C. Martineau, Javier Ortensi, Mark DeHart, 2019, Annals of Nuclear Energy.

PBMR-400 BENCHMARK SOLUTION OF EXERCISE 1 AND 2 USING THE MOOSE BASED APPLICATIONS: MAMMOTH, PRONGHORN

R. Martineau, M. DeHart, P. Balestra, 2021, EPJ Web of Conferences.

Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application

Zachary M. Prince, F. Kong, F. Gleicher, 2021 .

Fuel element design and analysis for potential LEU conversion of the Advanced Test Reactor

Michael A. Pope, Mark DeHart, Zain Karriem, 2017 .

Heat Source Characterization In A TREAT Fuel Particle Using Coupled Neutronics Binary Collision Monte-Carlo Calculations

Javier Ortensi, Mark DeHart, Daniel Schwen, 2017 .

Validation of the Griffin application for TREAT transient modeling and simulation

Matthew Johnson, F. Gleicher, M. DeHart, 2021, Nuclear Engineering and Design.

A Highly Parallel Multilevel Newton-Krylov-Schwarz Method with Subspace-Based Coarsening and Partition-Based Balancing for the Multigroup Neutron Transport Equation on Three-Dimensional Unstructured Meshes

Richard C. Martineau, Mark DeHart, Yaqi Wang, 2020, SIAM J. Sci. Comput..

Hybrid PN-SN with Lagrange multiplier and upwinding for the multiscale transport capability in Rattlesnake

Richard C. Martineau, Mark DeHart, Weixiong Zheng, 2017 .

A Newton solution for the Superhomogenization method: The PJFNK-SPH

Alain Hébert, Javier Ortensi, Mark DeHart, 2018 .

Engagement opportunities in OECD NEA benchmark development

P. Blaise, U. Rohatgi, A. Petruzzi, 2023, Frontiers in Energy Research.

Unstructured partial- and net-current based coarse mesh finite difference acceleration applied to the extended step characteristics method in NEWT

K. Kim, M. DeHart, 2011 .

SCALE 5 : Powerful New Criticality Safety Analysis Tools

D. F. Hollenbach, B. Rearden, S. Bowman, 2003 .

A Review of Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels

G. Ilas, M. DeHart, J. Bess, 2023, Journal of Nuclear Engineering.

Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel

C. V. Parks, John C. Wagner, Mark D. DeHart, 2000 .

Findings of an international study on burnup credit

M. C. Brady, M. C. Brady, E. Sartori, 1996 .

Automated Power-Following Control for Nuclear Thermal Propulsion Startup and Shutdown Using Moose-Based Applications

Zachary M. Prince, M. DeHart, C. Lin, 2023, SSRN Electronic Journal.

HTGR Reactor Physics and Burnup Calculations Using the Serpent Monte Carlo Code

Mark D. DeHart, Jaakko Leppänen, J. Leppänen, 2009 .

Lattice Physics Capabilities of the SCALE Code System Using TRITON

Mark D. DeHart, M. DeHart, 2006 .

TRITON: AN ADVANCED LATTICE CODE FOR MOX FUEL CALCULATIONS

T. J. Downar, Zhaopeng Zhong, M. D. DeHart, 2003 .

Reactor Physics Scoping and Characterization Study on Implementation of TRIGA Fuel in the Advanced Test Reactor

M. DeHart, J. Lyons, W. Marcum, 2015 .