Countries citing papers authored by Mark D. DeHart
Since
Specialization
Citations
This map shows the geographic impact of Mark D. DeHart's research. It shows the number of citations coming from papers published by authors working in each country. You can also color the map by specialization and compare the number of citations received by Mark D. DeHart with the expected number of citations based on a country's size and research output (numbers larger than one mean the country cites Mark D. DeHart more than expected).
This network shows the impact of papers produced by Mark D. DeHart. Nodes represent research fields, and links connect fields that are likely to share authors. Colored nodes show fields that tend to cite the papers produced by Mark D. DeHart. The network helps show where Mark D. DeHart may publish in the future.
Co-authorship network of co-authors of Mark D. DeHart
This figure shows the co-authorship network connecting the top 25 collaborators of Mark D. DeHart.
A scholar is included among the top collaborators of Mark D. DeHart based on the total number of
citations received by their joint publications. Widths of edges
represent the number of papers authors have co-authored together.
Node borders
signify the number of papers an author published with Mark D. DeHart. Mark D. DeHart is excluded from
the visualization to improve readability, since they are connected to all nodes in the network.
Ortensi, Javier, et al.. (2019). Implementation of Depletion Architecture in the MAMMOTH Reactor Physics Application. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information). 120(1). 905–906.1 indexed citations
8.
DeHart, Mark D., et al.. (2018). Weighted Delta-Tracking with Scattering. arXiv (Cornell University).1 indexed citations
9.
Avramova, Maria, Kostadin Ivanov, Mark D. DeHart, et al.. (2017). OECD/NEA EGMPEBV Activities in Multi-Physics Verification and Validation. Transactions of the American Nuclear Society. 116. 1297–1300.1 indexed citations
10.
Ganapol, B. D., et al.. (2016). Neutronic-Thermal hydraulic benchmark using the SKINATH point kinetics model. Transactions of the American Nuclear Society. 115. 600–603.1 indexed citations
11.
Ortensi, Javier, Michael A. Pope, Gerhard Strydom, et al.. (2011). PRISMATIC CORE COUPLED TRANSIENT BENCHMARK. University of North Texas Digital Library (University of North Texas). 104. 854–856.3 indexed citations
12.
Leppänen, Jaakko & Mark D. DeHart. (2009). HTGR Reactor Physics and Burnup Calculations Using the Serpent Monte Carlo Code. Transactions of the American Nuclear Society. 101. 782–784.15 indexed citations
13.
DeHart, Mark D., et al.. (2008). Validation of SCALE and the TRITON Depletion Sequence for Gas-Cooled Reactor Analysis. Transactions of the American Nuclear Society. 99. 683–685.1 indexed citations
14.
DeHart, Mark D.. (2007). High-fidelity depletion capabilities of the scale code system using triton. Transactions of the American Nuclear Society. 97. 598–600.4 indexed citations
15.
DeHart, Mark D. & L.M. Petrie. (2004). Integrated Keno v.a Monte Carlo transport for multidimensional depletion within scale. Transactions of the American Nuclear Society. 91. 667–669.1 indexed citations
16.
Parks, C.V., B.L. Broadhead, Mark D. DeHart, & Ian C Gauld. (2001). Validation Issues for Depletion and Criticality Analysis in Burnup Credit. University of North Texas Digital Library (University of North Texas).
17.
DeHart, Mark D.. (1999). A Deterministic Study of the Deficiency of the Wigner-Seitz Approximation for Pu/MOX Fuel Pins. University of North Texas Digital Library (University of North Texas).3 indexed citations
18.
Forsberg, Charles, et al.. (1996). Depleted-Uranium-Silicate Backfill of Spent-Fuel Waste Packages for Repository Containment and Criticality Control. High Level Radioactive Waste Management. 366–368.
19.
Takano, M., et al.. (1996). Findings of an International Study on Burnup Credit. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).2 indexed citations
20.
DeHart, Mark D., et al.. (1987). CENTAR code for extended nonlinear transient analysis of extraterrestrial reactor systems. Transactions of the American Nuclear Society. 55.
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