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Massimiliano Fratoni, Ph.D. - Publications

Affiliations: 
2004 Nuclear Engineering Università degli Studi di Roma La Sapienza, Roma, Lazio, Italy 
 2004-2008 Nuclear Engineering University of California, Berkeley, Berkeley, CA, United States 
Area:
Nuclear Engineering
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51 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 Keckler C, Fratoni M, Greenspan E. Sensitivity and Uncertainty Analysis of Neutron Spectrum and DPA in a B&B Core Nuclear Science and Engineering. 1-10. DOI: 10.1080/00295639.2020.1715688  0.539
2020 Keckler C, Fratoni M, Greenspan E. Neutronic impact of Autonomous Reactivity Control system inclusion in a breed-and-burn core Progress in Nuclear Energy. 126: 103395. DOI: 10.1016/J.Pnucene.2020.103395  0.565
2020 Keckler C, Robert Y, Fratoni M, Greenspan E. Development of methods for optimal assembly orificing design and application to a standing-wave Breed-and-Burn reactor Nuclear Engineering and Design. 365: 110706. DOI: 10.1016/J.Nucengdes.2020.110706  0.547
2020 Wooten D, Fratoni M. Linear optimization for predicting material compositions in molten salt reactors Annals of Nuclear Energy. 139: 107159. DOI: 10.1016/J.Anucene.2019.107159  0.352
2019 Alat E, Brova M, Younker I, Motta A, Fratoni M, Wolfe D. Neutronic and mechanical evaluation of rare earth doped and undoped nitride-based coatings for accident tolerant fuels Journal of Nuclear Materials. 518: 419-430. DOI: 10.1016/J.Jnucmat.2019.02.044  0.351
2019 Jolodosky A, Aufiero M, Fratoni M. Exact perturbation theory for fusion blanket design Annals of Nuclear Energy. 131: 353-366. DOI: 10.1016/J.Anucene.2019.03.039  0.713
2019 Atz M, Salazar A, Hirano F, Fratoni M, Ahn J. Assessment of the potential for criticality in the far field of a used nuclear fuel repository Annals of Nuclear Energy. 124: 28-38. DOI: 10.1016/J.Anucene.2018.09.028  0.505
2018 Hosemann P, Frazer D, Fratoni M, Bolind A, Ashby MF. Materials selection for nuclear applications: Challenges and opportunities Scripta Materialia. 143: 181-187. DOI: 10.1016/J.Scriptamat.2017.04.027  0.32
2018 Zhang G, Fratoni M, Greenspan E. Improved resource utilization by advanced burner reactors with breed-and-burn blankets Progress in Nuclear Energy. 106: 440-454. DOI: 10.1016/J.Pnucene.2018.03.020  0.695
2018 Woo SM, Chirayath SS, Fratoni M. Nuclide composition non-uniformity in used nuclear fuel for considerations in pyroprocessing safeguards Nuclear Engineering and Technology. 50: 1120-1130. DOI: 10.1016/J.Net.2018.05.011  0.628
2018 Zhang G, Fratoni M, Greenspan E. Fuel cycle analysis of Advanced Burner Reactor with breed-and-burn thorium blanket Annals of Nuclear Energy. 112: 383-394. DOI: 10.1016/J.Anucene.2017.10.016  0.678
2017 Hino T, Miwa J, Mitsuyasu T, Ishii Y, Ohtsuka M, Moriya K, Shirvan K, Seker V, Hall A, Downar T, Gorman PM, Fratoni M, Greenspan E. Core design and analysis of axially heterogeneous boiling water reactor for burning transuranium elements Nuclear Science and Engineering. 187: 213-239. DOI: 10.1080/00295639.2017.1312941  0.563
2017 Zhang G, Fratoni M, Greenspan E. Advanced burner reactors with breed-and-burn thorium blankets for improved economics and resource utilization Nuclear Technology. 199: 187-218. DOI: 10.1080/00295450.2017.1337408  0.664
2017 Fratoni M, Terrani KA. PWR core design with Metal Matrix Micro-encapsulated (M3) fuel Progress in Nuclear Energy. 100: 419-426. DOI: 10.1016/J.Pnucene.2017.07.009  0.411
2017 Qiu Y, Wang Z, Li K, Yuan Y, Wang K, Fratoni M. Calculation of adjoint-weighted kinetic parameters with the reactor Monte Carlo code RMC Progress in Nuclear Energy. 101: 424-434. DOI: 10.1016/J.Pnucene.2017.03.023  0.316
2017 Aufiero M, Fratoni M. A new approach to the stabilization and convergence acceleration in coupled Monte Carlo–CFD calculations: The Newton method via Monte Carlo perturbation theory Nuclear Engineering and Technology. 49: 1181-1188. DOI: 10.1016/J.Net.2017.08.005  0.769
2017 Kotlyar D, Aufiero M, Shwageraus E, Fratoni M. A perturbation-based susbtep method for coupled depletion Monte-Carlo codes Annals of Nuclear Energy. 102: 236-244. DOI: 10.1016/J.Anucene.2016.12.022  0.77
2016 Andreades C, Cisneros AT, Choi JK, Chong AYK, Fratoni M, Hong S, Huddar LR, Huff KD, Kendrick J, Krumwiede DL, Laufer MR, Munk M, Scarlat RO, Zweibaum N, Greenspan E, et al. Design summary of the Mark-I pebble-bed, fluoride salt-cooled, high-temperature reactor commercial power plant Nuclear Technology. 195: 223-238. DOI: 10.13182/Nt16-2  0.758
2016 Shapiro RA, Fratoni M. Assembly design of pressurized water reactors with fully ceramic microencapsulated fuel Nuclear Technology. 194: 15-27. DOI: 10.13182/Nt15-97  0.461
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  0.661
2016 Jolodosky A, Fratoni M, Meier W, Demuth J, Reyes S. Characterization of tritium breeding ratio and energy multiplication factor of lithium-based ternary alloys in IFE blankets Proceedings - Symposium On Fusion Engineering. 2016. DOI: 10.1109/SOFE.2015.7482359  0.332
2016 Younker I, Fratoni M. Neutronic evaluation of coating and cladding materials for accident tolerant fuels Progress in Nuclear Energy. 88: 10-18. DOI: 10.1016/J.Pnucene.2015.11.006  0.712
2016 Jolodosky A, Kramer K, Meier W, DeMuth J, Reyes S, Fratoni M. Neutronics and activation analysis of lithium-based ternary alloys in IFE blankets Fusion Engineering and Design. 107: 1-12. DOI: 10.1016/J.Fusengdes.2016.03.071  0.754
2016 Qiu Y, Aufiero M, Wang K, Fratoni M. Development of sensitivity analysis capabilities of generalized responses to nuclear data in Monte Carlo code RMC Annals of Nuclear Energy. 97: 142-152. DOI: 10.1016/J.Anucene.2016.07.016  0.777
2016 Aufiero M, Martin M, Fratoni M. XGPT: Extending Monte Carlo Generalized Perturbation Theory capabilities to continuous-energy sensitivity functions Annals of Nuclear Energy. DOI: 10.1016/J.Anucene.2016.06.012  0.776
2015 Gorman P, Bogetic S, Zhang G, Fratoni M, Vujic J, Greenspan E. The TRU-incinerating thorium RBWR core preliminary design 5th Topical Meeting On Advances in Nuclear Fuel Management, Anfm 2015: Advances in Nuclear Fuel Management V. 483-499.  0.319
2015 Younker I, Fratoni M. Neutronic and economic evaluation of accident tolerant fuel concepts for light water reactors 5th Topical Meeting On Advances in Nuclear Fuel Management, Anfm 2015: Advances in Nuclear Fuel Management V. 551-563.  0.369
2013 Shapiro RA, Younker IM, Fratoni M. Neutronic performance of accident tolerant fuels Transactions of the American Nuclear Society. 109: 1351-1353.  0.317
2011 Fratoni M, Greenspan E. Neutronic feasibility assessment of liquid salt-cooled pebble bed reactors Nuclear Science and Engineering. 168: 1-22. DOI: 10.13182/Nse10-38  0.62
2011 Latkowski JF, Abbott RP, Aceves S, Anklam T, Cook AW, DeMuth J, Divol L, El-Dasher B, Farmer JC, Flowers D, Fratoni M, Heltemes T, Kane J, Kramer KJ, Kramer R, et al. Chamber Design for the Laser Inertial Fusion Energy (LIFE) Engine Fusion Science and Technology. 60: 54-60. DOI: 10.13182/Fst10-318  0.34
2011 Kramer KJ, Fratoni M, Latkowski JF, Abbott RP, Anklam TM, Beckett EM, Bayramian AJ, DeMuth JA, Deri RJ, Rubia TDDL, Dunne AM, El-dasher BS, Farmer JC, Lafuente A, Meier WR, et al. Fusion-Fission Blanket Options for the LIFE Engine Fusion Science and Technology. 60: 72-77. DOI: 10.13182/Fst10-295  0.417
2011 Seifried JE, Fratoni M, Kramer KJ, Latkowski JF, Peterson PF, Powers JJ, Taylor JM. Adjoint-based uncertainty analysis for essential reactions in a laser inertial fusion engine Fusion Science and Technology. 60: 692-697. DOI: 10.13182/Fst10-291  0.642
2010 Fratoni M, Greenspan E. Equilibrium core composition search methodologies for pebble bed reactors Nuclear Science and Engineering. 166: 1-16. DOI: 10.13182/Nse09-66  0.592
2010 Kramer KJ, Latkowski JF, Abbott RP, Fratoni M, Powers JJ, Seifried JE, Taylor JM. The laser inertial fusion engine as a weapons grade plutonium fuel burner Transactions of the American Nuclear Society. 102: 91-92.  0.562
2010 Fratoni M, Kramer KJ, Latkowski JF, Abbott RP, Seifried JE, Powers JJ. Attainable burnup in a life engine loaded with depleted uranium International Conference On the Physics of Reactors 2010, Physor 2010. 3: 2157-2166.  0.604
2010 Seifried JE, Abbott RP, Fratoni M, Kramer KJ, Latkowski JF, Peterson PF, Powers JJ, Taylor JM. Explicit uncertainty analysis for tritium breeding in a laser inertial fusion engine Transactions of the American Nuclear Society. 102: 250-251.  0.528
2009 Monti L, Lee K, Fratoni M, Sumini M, Greenspan E. Recycling-Independent Core Design for the ENHS Fuel Self-Sustaining Reactor Nuclear Science and Engineering. 161: 1-21. DOI: 10.13182/Nse162-01  0.576
2009 Fratoni M, Greenspan E. Neutronic design of hydride fueled BWRs Nuclear Engineering and Design. 239: 1531-1543. DOI: 10.1016/J.Nucengdes.2009.01.016  0.642
2009 Greenspan E, Fratoni M, Ganda F, Ginex F, Olander D, Todreas N, Diller P, Ferroni P, Malen J, Romano A, Shuffler C, Trant J, Petrovic B, Garkisch H. Hydride fuel for LWRs-Project overview Nuclear Engineering and Design. 239: 1374-1405. DOI: 10.1016/J.Nucengdes.2008.11.023  0.801
2009 Fratoni M, Greenspan E, Peterson PF. Coupling of MCNP and ORIGEN2 for pebble bed reactors depletion analysis Transactions of the American Nuclear Society. 101: 785-786.  0.454
2008 Monti L, Greenspan E, Sumini M, Fratoni M, Lee KB, Rocchi F. Multi-recycling in the ENHS and the equilibrium core Progress in Nuclear Energy. 50: 262-268. DOI: 10.1016/J.Pnucene.2007.11.008  0.575
2008 Becker B, Fratoni M, Greenspan E. Feasibility of a critical molten salt reactor for waste transmutation Progress in Nuclear Energy. 50: 236-241. DOI: 10.1016/J.Pnucene.2007.11.004  0.623
2008 Greenspan E, Hong SG, Lee KB, Monti L, Okawa T, Susplugas A, Fratoni M, Kim L, Mattafirri S, Petroski R. Innovations in the ENHS reactor design and fuel cycle Progress in Nuclear Energy. 50: 129-139. DOI: 10.1016/J.Pnucene.2007.10.022  0.61
2008 Fratoni M, Greenspan E, Peterson PF. Neutronic analysis of the PB-AHTR integral design International Conference On the Physics of Reactors 2008, Physor 08. 2: 1563-1570.  0.554
2007 Fratoni M, Greenspan E. Determination of the equilibrium composition of cores with continuous fuel feed and removal using MOCUP Joint International Topical Meeting On Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + Sna 2007.  0.557
2007 Fratoni M, Greenspan E, Peterson PF. Neutronic and depletion analysis of the PB-AHTR Global 2007: Advanced Nuclear Fuel Cycles and Systems. 856-865.  0.319
2006 Ginex F, Ganda F, Fratoni M, Greenspan E. One-dimensional neutronic analysis of BWR hydride fuel bundles Physor-2006 - American Nuclear Society's Topical Meeting On Reactor Physics. 2006.  0.76
2006 Ferroni P, Fratoni M, Ginex F, Ganda F, Handwerk C, Greenspan E, Todreas N. Feasibility of improving BWR performance using hydride fuel Proceedings of the 2006 International Congress On Advances in Nuclear Power Plants, Icapp'06. 2006: 95-103.  0.766
2006 Fratoni M, Greenspan E. Optimal hydride fueled BWR assembly designs Physor-2006 - American Nuclear Society's Topical Meeting On Reactor Physics. 2006.  0.59
2004 Fratoni M, Barnes D, Greenspan E, Gandini A. Design and analysis of Molten Salt Reactor fueled by TRU from LWR Proceedings of the Physor 2004: the Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. 2129-2136.  0.499
2004 Rodriguez-Vieitez E, Fratoni M, Greenspan E. Spectrum-dependent transmutation efficiency in molten salt reactors Transactions of the American Nuclear Society. 90: 43-45.  0.458
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