Year |
Citation |
Score |
2019 |
Salko RK, Pointer WD, Delchini M, Gurecky WL, Clarno KT, Salttery SR, Petrov V, Manera A. Implementation of a Spacer Grid Rod Thermal-Hydraulic Reconstruction (ROTHCON) Capability into the Thermal-Hydraulic Subchannel Code CTF Nuclear Technology. 205: 1697-1706. DOI: 10.1080/00295450.2019.1585734 |
0.402 |
|
2019 |
Toptan A, Salko RK, Avramova MN, Clarno K, Kropaczek DJ. A new fuel modeling capability, CTFFuel, with a case study on the fuel thermal conductivity degradation Nuclear Engineering and Design. 341: 248-258. DOI: 10.1016/J.Nucengdes.2018.11.010 |
0.416 |
|
2019 |
Kim KS, Williams ML, Wiarda D, Clarno KT. Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Method and procedure Annals of Nuclear Energy. 133: 46-58. DOI: 10.1016/J.Anucene.2019.05.010 |
0.466 |
|
2018 |
Capps N, Stimpson S, Clarno K, Wirth BD, Rashid J. Assessment of the analysis capability for core-wide PWR pellet-clad interaction screening of Watts Bar Unit 1 Nuclear Engineering and Design. 333: 131-144. DOI: 10.1016/J.Nucengdes.2018.04.018 |
0.441 |
|
2018 |
Stimpson S, Powers J, Clarno K, Pawlowski R, Gardner R, Novascone S, Gamble K, Williamson R. Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1–3 Nuclear Engineering and Design. 327: 172-186. DOI: 10.1016/J.Nucengdes.2017.12.015 |
0.448 |
|
2017 |
Kochunas B, Collins B, Stimpson S, Salko R, Jabaay D, Graham A, Liu Y, Kim KS, Wieselquist W, Godfrey A, Clarno K, Palmtag S, Downar T, Gehin J. VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion Nuclear Science and Engineering. 185: 217-231. DOI: 10.13182/Nse16-39 |
0.451 |
|
2017 |
Stimpson S, Liu Y, Collins B, Clarno K. A lumped parameter method of characteristics approach and multigroup kernels applied to the subgroup self-shielding calculation in MPACT Nuclear Engineering and Technology. 49: 1240-1249. DOI: 10.1016/J.Net.2017.07.006 |
0.413 |
|
2016 |
Turner JA, Clarno K, Sieger M, Bartlett R, Collins B, Pawlowski R, Schmidt R, Summers R. The Virtual Environment for Reactor Applications (VERA): Design and architecture Journal of Computational Physics. 326: 544-568. DOI: 10.1016/J.Jcp.2016.09.003 |
0.383 |
|
2016 |
Hamilton S, Berrill M, Clarno K, Pawlowski R, Toth A, Kelley CT, Evans T, Philip B. An assessment of coupling algorithms for nuclear reactor core physics simulations Journal of Computational Physics. 311: 241-257. DOI: 10.1016/J.Jcp.2016.02.012 |
0.459 |
|
2015 |
Philip B, Berrill MA, Allu S, Hamilton SP, Sampath RS, Clarno KT, Dilts GA. A parallel multi-domain solution methodology applied to nonlinear thermal transport problems in nuclear fuel pins Journal of Computational Physics. 286: 143-171. DOI: 10.1016/J.Jcp.2015.01.029 |
0.459 |
|
2014 |
Schmidt R, Belcourt K, Hooper R, Pawlowski R, Clarno K, Simunovic S, Slattery S, Turner J, Palmtag S. An approach for coupled-code multiphysics core simulations from a common input Annals of Nuclear Energy. DOI: 10.1016/J.Anucene.2014.11.015 |
0.475 |
|
2013 |
Piro MHA, Banfield J, Clarno KT, Simunovic S, Besmann TM, Lewis BJ, Thompson WT. Coupled thermochemical, isotopic evolution and heat transfer simulations in highly irradiated UO2 nuclear fuel Journal of Nuclear Materials. 441: 240-251. DOI: 10.1016/J.Jnucmat.2013.05.060 |
0.368 |
|
2012 |
Clarno KT, Philip B, Cochran WK, Sampath RS, Allu S, Barai P, Simunovic S, Berrill MA, Ott LJ, Pannala S, Dilts GA, Mihaila B, Yesilyurt G, Lee JH, Banfield JE. The AMP (Advanced MultiPhysics) nuclear fuel performance code Nuclear Engineering and Design. 252: 108-120. DOI: 10.1016/J.Nucengdes.2012.07.018 |
0.455 |
|
2012 |
Banfield JE, Clarno KT, Hamilton SP, Maldonado GI, Philip B, Baird ML. Benchmarking of software and methods for use in transient multidimensional fuel performance with spatial reactor kinetics International Congress On Advances in Nuclear Power Plants 2012, Icapp 2012. 3: 1685-1694. |
0.367 |
|
2011 |
Yesilyurt G, Clarno KT, Evans TM, Davidson GG, Fox PB. A C5 benchmark problem with the discrete ordinates radiation transport code denovo Nuclear Technology. 176: 274-283. DOI: 10.13182/Nt11-A13301 |
0.348 |
|
2010 |
Evans TM, Stafford AS, Slaybaugh RN, Clarno KT. Denovo: A new three-dimensional parallel discrete ordinates code in SCALE Nuclear Technology. 171: 171-200. DOI: 10.13182/Nt171-171 |
0.371 |
|
2010 |
Evans TM, Clarno KT, Morel JE. A Transport Acceleration Scheme for Multigroup Discrete Ordinates with Upscattering Nuclear Science and Engineering. 165: 292-304. DOI: 10.13182/Nse09-28 |
0.362 |
|
2008 |
Williams DF, Clarno KT. Evaluation of salt coolants for reactor applications Nuclear Technology. 163: 330-343. DOI: 10.13182/Nt08-A3992 |
0.329 |
|
2008 |
Zhong Z, Downar TJ, Xu Y, DeHart MD, Clarno KT. Implementation of two-level coarse-mesh finite difference acceleration in an arbitrary geometry, two-dimensional discrete ordinates transport method Nuclear Science and Engineering. 158: 289-298. DOI: 10.13182/Nse06-24Tn |
0.398 |
|
2007 |
Ganapol BD, Clarno KT, Johnson S, De Oliveira C, Hamilton S. An embedded semi-analytical benchmark via iterative interpolation for neutron transport methods verification Joint International Topical Meeting On Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + Sna 2007. |
0.32 |
|
2005 |
Clarno KT, Adams ML. Capturing the Effects of Unlike Neighbors in Single-Assembly Calculations Nuclear Science and Engineering. 149: 182-196. DOI: 10.13182/Nse04-31 |
0.502 |
|
2005 |
Clarno KT, Adams ML. Capturing the effects of unlike neighbors in single-assembly calculations Nuclear Science and Engineering. 149: 182-196. |
0.384 |
|
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