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Michael L. Fensin, Ph.D. - Publications

Affiliations: 
2008 University of Florida, Gainesville, Gainesville, FL, United States 
Area:
Nuclear Engineering
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12 high-probability publications. We are testing a new system for linking publications to authors. You can help! If you notice any inaccuracies, please sign in and mark papers as correct or incorrect matches. If you identify any major omissions or other inaccuracies in the publication list, please let us know.

Year Citation  Score
2019 Rolison LM, Fensin ML, Thio YCF, Hsu SC, Cruz EJ. Neutronics Calculations for a Hypothetical Plasma-Jet-Driven Magneto-Inertial-Fusion Reactor Fusion Science and Technology. 75: 438-451. DOI: 10.1080/15361055.2019.1613140  0.313
2016 Adigun BJ, Fensin ML, Galloway JD, Trellue HR. Maintaining a critical spectra within Monteburns for a gas-cooled reactor array by way of control rod manipulation Annals of Nuclear Energy. 96: 36-60. DOI: 10.1016/J.Anucene.2016.05.025  0.356
2016 Fensin ML, James MR. Biasing secondary particle interaction physics and production in MCNP6 Annals of Nuclear Energy. 94: 618-625. DOI: 10.1016/J.Anucene.2016.03.025  0.407
2016 Goorley T, James M, Booth T, Brown F, Bull J, Cox LJ, Durkee J, Elson J, Fensin M, Forster RA, Hendricks J, Hughes HG, Johns R, Kiedrowski B, Martz R, et al. Features of MCNP6 Annals of Nuclear Energy. 87: 772-783. DOI: 10.1016/J.Anucene.2015.02.020  0.477
2015 Fensin ML, Umbel M. Testing actinide fission yield treatment in CINDER90 for use in MCNP6 burnup calculations Progress in Nuclear Energy. 85: 719-728. DOI: 10.1016/J.Pnucene.2015.09.001  0.431
2015 Fensin ML, Galloway JD, James MR. Performance upgrades to the MCNP6 burnup capability for large scale depletion calculations Progress in Nuclear Energy. 83: 186-190. DOI: 10.1016/J.Pnucene.2015.03.017  0.471
2015 Weldon RA, Fensin ML, Trellue HR. Total neutron emission generation and characterization for a Next Generation Safeguards Initiative spent fuel library Progress in Nuclear Energy. 80: 45-73. DOI: 10.1016/J.Pnucene.2014.10.012  0.323
2015 Richard J, Galloway J, Fensin M, Trellue H. SMITHERS: An object-oriented modular mapping methodology for MCNP-based neutronic-thermal hydraulic multiphysics Annals of Nuclear Energy. 81: 150-163. DOI: 10.1016/J.Anucene.2015.03.027  0.373
2014 Weldon RA, Fensin ML, McKinney GW. Testing the delayed gamma capability in MCNP6 18th Topical Meeting of the Radiation Protection and Shielding Division of Ans, Rpsd 2014. 234-237. DOI: 10.13182/Nt14-127  0.37
2012 Goorley T, James M, Booth T, Brown F, Bull J, Cox LJ, Durkee J, Elson J, Fensin M, Forster RA, Hendricks J, Hughes HG, Johns R, Kiedrowski B, Martz R, et al. Initial MCNP6 Release Overview Nuclear Technology. 180: 298-315. DOI: 10.13182/Nt11-135  0.395
2010 Fensin ML, Hendricks JS, Anghaie S. The enhancements and testing for the mcnpx 2.6.0 depletion capability Nuclear Technology. 170: 68-79. DOI: 10.13182/Nt10-2  0.543
2008 Fensin ML, Hendricks JS, Anghaie S. Improved reaction rate tracking and fission product yield determinations for the Monte Carlo-linked depletion capability in MCNPX Nuclear Technology. 164: 3-12. DOI: 10.13182/Nt08-A4003  0.536
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