Mark DeHart
Mark DeHart
Directorate Fellow, Idaho National Laboratory
Verified email at inl.gov
Title
Cited by
Cited by
Year
NEWT: a new transport algorithm for two-dimensional discrete ordinates analysis in non-orthogonal geometries
MD DeHart, MD Jessee
ORNL/TM-2005/39, Oak Ridge National Laboratory, 2005
1042005
Reactor physics methods and analysis capabilities in SCALE
MD DeHart, SM Bowman
Nuclear Technology 174 (2), 196-213, 2011
982011
Triton: a two-dimensional transport and depletion module for characterization of spent nuclear fuel
MD DeHart
ORNL/TM-2005/39, Version 6, 2006
932006
OECD/NEA burnup credit calculational criticality benchmark phase IB results
MD DeHart, CV Parks, MC Brady
ORNL, 1996
701996
Sensitivity and parametric evaluations of significant aspects of burnup credit for PWR spent fuel packages
MD DeHart
Oak Ridge National Lab., 1996
681996
Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages
JJ Lichtenwalter, SM Bowman, MD DeHart, CM Hopper
Nuclear Regulatory Commission, 1997
631997
Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel
CV Parks
ORNL Oak Ridge National Laboratory (United States). Funding organisation: US …, 2000
512000
Baseline Assessment of TREAT for Modeling and Analysis Needs
JD Bess, MD DeHart
Idaho National Laboratory (INL), 2015
502015
Review of axial burnup distribution considerations for burnup credit calculations
JC Wagner, MD DeHart
Oak Ridge National Lab., TN (US), 2000
482000
An extension of the validation of SCALE (SAS2H) isotopic predictions for PWR spent fuel
MD DeHart, OW Hermann
Oak Ridge National Lab., 1996
471996
TRITON: a two-dimensional depletion sequence for characterization of spent nuclear fuel
MD DeHart
ORNL/TM-2005/39, Oak Ridge National Laboratory, 2005
422005
Validation of SCALE (SAS2H) isotopic predictions for BWR spent fuel
OW Hermann, MD DeHart
Oak Ridge National Lab., 1998
411998
Validation of the SCALE Broad Structure 44-Group ENDF/BV Cross-Section Library for Use in Criticality Safety Analyses
MD DeHart, SM Bowman
Nuclear Regulatory Commission, Washington, DC (United States). Div. of …, 1994
361994
Development of generalized perturbation theory capability within the SCALE code package
MA Jessee, ML Williams, MD Dehart
Proceedings of M&C, 2009
342009
Triton: a multipurpose transport, depletion, and sensitivity and uncertainty analysis module
MA Jessee, MD DeHart
Oak Ridge National Laboratory, ORNL/TM-2005/39 Version 6, 2011
322011
Implementation of two-level coarse-mesh finite difference acceleration in an arbitrary geometry, two-dimensional discrete ordinates transport method
Z Zhong, TJ Downar, Y Xu, MD DeHart, KT Clarno
Nuclear science and engineering 158 (3), 289-298, 2008
302008
Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel
BL Broadhead, MD DeHart, JC Ryman, JS Tang, CV Parks
Oak Ridge National Lab., 1995
301995
HTGR reactor physics and burnup calculations using the Serpent Monte Carlo code
J Leppänen, M DeHart
Trans. Am. Nucl. Soc 101, 782, 2009
292009
An extended step characteristic method for solving the transport equation in general geometries
MD DeHart, RE Pevey, TA Parish
Nuclear Science and Engineering 118 (2), 79-90, 1994
271994
A DISCRETE ORDINATES APPROXIMATION TO THE NEUTRON TRANSPORT EQUATION APPLIED TO GENERALIZED GEOMETRIES (U)
MD DeHart
https://www.osti.gov/servlets/purl/10173922, 1992
271992
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