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Nicholas R. Brown - Publications

Affiliations: 
2007-2011 School of Nuclear Engineering Purdue University, West Lafayette, IN, United States 
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58 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
2020 Lee SK, Liu M, Brown NR, Terrani KA, Lee Y. Effect of Heater Material and Thickness on the Steady-State Flow Boiling Critical Heat Flux Nuclear Technology. 206: 339-346. DOI: 10.1080/00295450.2019.1670010  0.324
2020 Brown NR, Diamond DJ, Bajorek S, Denning R. Thermal-Hydraulic and Neutronic Phenomena Important in Modeling and Simulation of Liquid-Fuel Molten Salt Reactors Nuclear Technology. 206: 322-338. DOI: 10.1080/00295450.2019.1590077  0.411
2020 Hernandez R, Folsom CP, Woolstenhulme NE, Jensen CB, Bess JD, Gorton JP, Brown NR. Review of pool boiling critical heat flux (CHF) and heater rod design for CHF experiments in TREAT Progress in Nuclear Energy. 123: 103303. DOI: 10.1016/J.Pnucene.2020.103303  0.413
2020 Duchnowski EM, Kile RF, Snead LL, Trelewicz JR, Brown NR. Reactor performance and safety characteristics of two-phase composite moderator concepts for modular high temperature gas cooled reactors Nuclear Engineering and Design. 368: 110824. DOI: 10.1016/J.Nucengdes.2020.110824  0.47
2020 Gorton JP, Collins BS, Wysocki AJ, Brown NR. Assessment of CASL VERA for BWR analysis and application to accident tolerant SiC/SiC channel box Nuclear Engineering and Design. 365: 110732. DOI: 10.1016/J.Nucengdes.2020.110732  0.369
2020 Singh G, Gorton J, Schappel D, Collins B, Katoh Y, Brown N, Wirth B. Impact of control blade insertion on the deformation behavior of SiC-SiC channel boxes in BWRs Nuclear Engineering and Design. 363: 110621. DOI: 10.1016/J.Nucengdes.2020.110621  0.332
2020 Gorton JP, Schappel D, Nelson AT, Brown NR. Impact of uranium oxide (UO2) fuel with molybdenum (Mo) inserts on pressurized water reactor performance and safety Journal of Nuclear Materials. 542: 152492. DOI: 10.1016/J.Jnucmat.2020.152492  0.486
2020 Brown NR, Garrison BE, Lowden RR, Cinbiz MN, Linton KD. Mechanical failure of fresh nuclear grade iron–chromium–aluminum (FeCrAl) cladding under simulated hot zero power reactivity initiated accident conditions Journal of Nuclear Materials. 539: 152352. DOI: 10.1016/J.Jnucmat.2020.152352  0.369
2020 Kane KA, Lee SK, Bell SB, Brown NR, Pint BA. Burst behavior of nuclear grade FeCrAl and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions Journal of Nuclear Materials. 539: 152256. DOI: 10.1016/J.Jnucmat.2020.152256  0.358
2020 Brown NR. A review of in-pile fuel safety tests of TRISO fuel forms and future testing opportunities in non-HTGR applications Journal of Nuclear Materials. 534: 152139. DOI: 10.1016/J.Jnucmat.2020.152139  0.413
2020 Schappel D, Brown NR, Terrani KA. Modeling reactivity insertion experiments of TRISO particles in NSRR using BISON Journal of Nuclear Materials. 530: 151965. DOI: 10.1016/J.Jnucmat.2019.151965  0.344
2020 Lee SK, Lee Y, Brown NR, Terrani KA. Elucidating the Impact of Flow on Material-Sensitive Critical Heat Flux and Boiling Heat Transfer Coefficients: An Experimental Study with Various Materials International Journal of Heat and Mass Transfer. 158: 119970. DOI: 10.1016/J.Ijheatmasstransfer.2020.119970  0.372
2020 Hernandez R, Brown NR. Potential fuel cycle performance of floating small modular light water reactors of Russian origin Annals of Nuclear Energy. 144: 107555. DOI: 10.1016/J.Anucene.2020.107555  0.444
2020 Burns JR, Hernandez R, Terrani KA, Nelson AT, Brown NR. Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5 Annals of Nuclear Energy. 142: 107423. DOI: 10.1016/J.Anucene.2020.107423  0.44
2019 Gorton JP, Collins BS, Nelson AT, Brown NR. Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR Nuclear Engineering and Design. 355: 110317. DOI: 10.1016/J.Nucengdes.2019.110317  0.454
2019 Betzler BR, Heidet F, Feng B, Rabiti C, Sofu T, Brown NR. Modeling and simulation functional needs for molten salt reactor licensing Nuclear Engineering and Design. 355: 110308. DOI: 10.1016/J.Nucengdes.2019.110308  0.382
2019 Gorton JP, Lee SK, Lee Y, Brown NR. Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties Nuclear Engineering and Design. 353: 110295. DOI: 10.1016/J.Nucengdes.2019.110295  0.436
2019 Lu C, Brown NR. Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost Nuclear Engineering and Design. 347: 108-121. DOI: 10.1016/J.Nucengdes.2019.03.022  0.434
2019 Lu C, Koyanagi T, Katoh Y, Strydom G, Terrani KA, Brown NR. Fully Ceramic Microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Sensitivity of reactor behavior during design basis accidents to fuel properties and the potential impact of the SiC defect annealing process Nuclear Engineering and Design. 345: 125-147. DOI: 10.1016/J.Nucengdes.2019.02.012  0.429
2019 Aly Z, Casagranda A, Pastore G, Brown NR. Variance-based sensitivity analysis applied to hydrogen migration and redistribution model in Bison. Part I: Simulation of historical experiments Journal of Nuclear Materials. 524: 90-100. DOI: 10.1016/J.Jnucmat.2019.06.035  0.396
2019 Aly Z, Casagranda A, Pastore G, Brown NR. Variance-based sensitivity analysis applied to the hydrogen migration and redistribution model in Bison. Part II: Uncertainty quantification and optimization Journal of Nuclear Materials. 523: 478-489. DOI: 10.1016/J.Jnucmat.2019.06.023  0.387
2019 Singh G, Gorton J, Schappel D, Brown N, Katoh Y, Wirth B, Terrani K. Deformation analysis of SiC-SiC channel box for BWR applications Journal of Nuclear Materials. 513: 71-85. DOI: 10.1016/J.Jnucmat.2018.10.045  0.374
2019 Lee SK, Liu M, Brown NR, Terrani KA, Blandford ED, Ban H, Jensen CB, Lee Y. Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel International Journal of Heat and Mass Transfer. 132: 643-654. DOI: 10.1016/J.Ijheatmasstransfer.2018.11.141  0.347
2019 Hernandez R, Todosow M, Brown NR. Micro heat pipe nuclear reactor concepts: Analysis of fuel cycle performance and environmental impacts Annals of Nuclear Energy. 126: 419-426. DOI: 10.1016/J.Anucene.2018.11.050  0.472
2019 Leandro AM, Heidet F, Hu R, Brown NR. Thermal hydraulic model of the molten salt reactor experiment with the NEAMS system analysis module Annals of Nuclear Energy. 126: 59-67. DOI: 10.1016/J.Anucene.2018.10.060  0.428
2018 Ali AF, Gorton JP, Brown NR, Terrani KA, Jensen CB, Lee Y, Blandford ED. Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys Nuclear Engineering and Design. 338: 218-231. DOI: 10.1016/J.Nucengdes.2018.08.024  0.354
2018 Singh G, Sweet R, Brown N, Wirth B, Katoh Y, Terrani K. Parametric Evaluation of SiC/SiC Composite Cladding with UO2 Fuel for LWR Applications: Fuel Rod Interactions and Impact of Nonuniform Power Profile in Fuel Rod Journal of Nuclear Materials. 499: 155-167. DOI: 10.1016/J.Jnucmat.2017.10.059  0.453
2018 Losa E, Košťál M, Czakoj T, Jánský B, Novák E, Rypar V, Powers JJ, Brown NR, Mueller D. Neutronic experiments with fluorine rich compounds at LR-0 reactor Annals of Nuclear Energy. 120: 286-295. DOI: 10.1016/J.Anucene.2018.05.056  0.306
2018 Powers JJ, Brown NR, Mueller DE, Patton BW, Losa E, Košťál M. Sensitivity/uncertainty analyses comparing LR-0 reactor experiments containing FLiBe salt with models for molten-salt-cooled and molten-salt-fueled reactors Annals of Nuclear Energy. 120: 319-332. DOI: 10.1016/J.Anucene.2018.05.052  0.424
2018 Lu C, Hiscox BD, Terrani KA, Brown NR. Fully ceramic microencapsulated fuel in prismatic high temperature gas-cooled reactors: Analysis of reactor performance and safety characteristics Annals of Nuclear Energy. 114: 277-287. DOI: 10.1016/J.Anucene.2017.12.021  0.457
2017 Burns JR, Brown NR. Neutron cross section sensitivity and uncertainty analysis of candidate accident tolerant fuel concepts Annals of Nuclear Energy. 110: 1249-1255. DOI: 10.1016/J.Anucene.2017.08.004  0.386
2017 Liu M, Brown NR, Terrani KA, Ali AF, Blandford ED, Wachs DM. Potential impact of accident tolerant fuel cladding critical heat flux characteristics on the high temperature phase of reactivity initiated accidents Annals of Nuclear Energy. 110: 48-62. DOI: 10.1016/J.Anucene.2017.06.016  0.423
2017 Cinbiz MN, Brown NR, Terrani KA, Lowden RR, Erdman D. A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding Annals of Nuclear Energy. 109: 396-404. DOI: 10.1016/J.Anucene.2017.05.058  0.354
2017 McMurray JW, Lindemer TB, Brown NR, Reif TJ, Morris RN, Hunn JD. Determining the minimum required uranium carbide content for HTGR UCO fuel kernels Annals of Nuclear Energy. 104: 237-242. DOI: 10.1016/J.Anucene.2017.02.023  0.397
2017 Brown NR, Betzler BR, Carbajo JJ, Wysocki AJ, Greenwood MS, Gentry C, Qualls AL. Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis Annals of Nuclear Energy. 103: 49-59. DOI: 10.1016/J.Anucene.2017.01.003  0.444
2017 Qualls AL, Betzler BR, Brown NR, Carbajo JJ, Greenwood MS, Hale R, Harrison TJ, Powers JJ, Robb KR, Terrell J, Wysocki AJ, Gehin JC, Worrall A. Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview Annals of Nuclear Energy. 107: 144-155. DOI: 10.1016/J.Anucene.2016.11.021  0.444
2017 Brown NR, Worrall A, Todosow M. Impact of thermal spectrum small modular reactors on performance of once-through nuclear fuel cycles with low-enriched uranium Annals of Nuclear Energy. 101: 166-173. DOI: 10.1016/J.Anucene.2016.11.003  0.439
2017 Brown NR, Wysocki AJ, Terrani KA, Xu KG, Wachs DM. The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors Annals of Nuclear Energy. 99: 353-365. DOI: 10.1016/J.Anucene.2016.09.033  0.409
2016 Brown NR, Powers JJ, Todosow M, Fratoni M, Ludewig H, Sunny EE, Raitses G, Aronson A. Thorium fuel cycles with externally driven systems Nuclear Technology. 194: 233-251. DOI: 10.13182/Nt15-40  0.417
2016 Brown NR, Carlsen BW, Dixon BW, Feng B, Greenberg HR, Hays RD, Passerini S, Todosow M, Worrall A. Identification of fuel cycle simulator functionalities for analysis of transition to a new fuel cycle Annals of Nuclear Energy. 96: 88-95. DOI: 10.1016/J.Anucene.2016.05.027  0.39
2016 Feng B, Dixon B, Sunny E, Cuadra A, Jacobson J, Brown NR, Powers J, Worrall A, Passerini S, Gregg R. Standardized verification of fuel cycle modeling Annals of Nuclear Energy. 94: 300-312. DOI: 10.1016/J.Anucene.2016.03.002  0.378
2015 Baek JS, Cuadra A, Cheng LY, Hanson AL, Brown NR, Diamond DJ. Analysis of loss-of-flow accidents for the nist research reactor with fuel conversion from heu to leu Nuclear Technology. 189: 71-86. DOI: 10.13182/Nt13-124  0.413
2015 Heidet F, Brown NR, Tahar MH. Accelerator Reactor Coupling for Energy Production in Advanced Nuclear Fuel Cycles Reviews of Accelerator Science and Technology. 8: 99-114. DOI: 10.1142/S1793626815300066  0.399
2015 Brown NR, Powers JJ, Feng B, Heidet F, Stauff NE, Zhang G, Todosow M, Worrall A, Gehin JC, Kim TK, Taiwo TA. Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems Nuclear Engineering and Design. 289: 252-265. DOI: 10.1016/J.Nucengdes.2015.04.015  0.435
2015 Brown NR, Todosow M, Cuadra A. Screening of advanced cladding materials and UN-U3Si5 fuel Journal of Nuclear Materials. 462: 26-42. DOI: 10.1016/J.Jnucmat.2015.03.016  0.395
2014 Baek JS, Cuadra A, Cheng LY, Hanson AL, Brown NR, Diamond DJ. Analysis of reactivity insertion accidents for the NIST research reactor before and after fuel conversion Nuclear Technology. 185: 1-20. DOI: 10.13182/Nt13-26  0.444
2014 Brown NR, Hanson AL, Diamond DJ. Impact of local burnup on prediction of power density in the NIST research reactor Nuclear Technology. 187: 103-116. DOI: 10.13182/Nt13-20  0.374
2014 Brown NR, Aronson A, Todosow M, Brito R, McClellan KJ. Neutronic performance of uranium nitride composite fuels in a PWR Nuclear Engineering and Design. 275: 393-407. DOI: 10.1016/J.Nucengdes.2014.04.040  0.394
2013 Brown NR, Ludewig H, Aronson A, Raitses G, Todosow M. Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback Annals of Nuclear Energy. 62: 548-557. DOI: 10.1016/J.Anucene.2013.05.027  0.443
2013 Brown NR, Ludewig H, Aronson A, Raitses G, Todosow M. Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients Annals of Nuclear Energy. 62: 538-547. DOI: 10.1016/J.Anucene.2013.05.025  0.42
2012 Brown NR, Seker V, Revankar ST, Downar TJ. Transient simulation of an endothermic chemical process facility coupled to a high temperature reactor: Model development and validation Nuclear Engineering and Design. 248: 1-13. DOI: 10.1016/J.Nucengdes.2012.03.049  0.665
2012 Brown NR, Seker V, Revankar ST, Downar TJ. An endothermic chemical process facility coupled to a high temperature reactor. Part I: Proposed accident scenarios within the chemical plant Nuclear Engineering and Design. 246: 256-265. DOI: 10.1016/J.Nucengdes.2011.12.027  0.649
2012 Brown NR, Revankar ST. An endothermic chemical process facility coupled to a high temperature reactor. Part II: Transient simulation of accident scenarios within the chemical plant Nuclear Engineering and Design. 246: 266-276. DOI: 10.1016/J.Nucengdes.2011.12.026  0.659
2012 Brown NR, Revankar ST. A review of catalytic sulfur (VI) oxide decomposition experiments International Journal of Hydrogen Energy. 37: 2685-2698. DOI: 10.1016/J.Ijhydene.2011.10.054  0.597
2010 Brown NR, Revankar ST, Seker V, Downar TJ. Proposed chemical plant initiated accident scenarios in a sulphur-iodine cycle plant coupled to a pebble bed modular reactor Nuclear Science. 377-386. DOI: 10.1787/9789264087156-43-En  0.635
2010 Brown NR, Seker V, Oh S, Revankar ST, Downar TJ, Kane C. Transient modelling of sulphur-iodine cycle thermochemical hydrogen generation coupled to pebble bed modular reactor Nuclear Science. 363-376. DOI: 10.1787/9789264087156-42-En  0.724
2009 Brown NR, Oh S, Revankar ST, Vierow K, Rodriguez S, Cole R, Gauntt R. Simulation of sulfur-iodine thermochemical hydrogen production plant coupled to high-temperature heat source Nuclear Technology. 167: 95-106. DOI: 10.13182/Nt09-A8854  0.695
2009 Brown NR, Oh S, Revankar ST, Kane C, Rodriguez S, Cole R, Gauntt R. Analysis model for sulfur-iodine and hybrid sulfur thermochemical cycles Nuclear Technology. 166: 43-55. DOI: 10.13182/Nt09-A6967  0.711
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