| 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 |
0.652 |
|
| 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 |
0.694 |
|
| 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 |
0.693 |
|
| 2019 |
Seifried JE, Scarlat RO, Peterson PF, Greenspan E. A general approach for determination of acceptable FLiBe impurity concentrations in Fluoride-Salt Cooled High Temperature Reactors (FHRs) Nuclear Engineering and Design. 343: 85-95. DOI: 10.1016/J.Nucengdes.2018.09.038 |
0.349 |
|
| 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 |
0.799 |
|
| 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 |
0.781 |
|
| 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 |
0.693 |
|
| 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 |
0.789 |
|
| 2017 |
Qvist SA, Hellesen C, Gradecka M, Dubberley AE, Fanning T, Greenspan E. Tailoring the response of Autonomous Reactivity Control (ARC) systems Annals of Nuclear Energy. 99: 383-398. DOI: 10.1016/J.Anucene.2016.09.036 |
0.748 |
|
| 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 |
0.787 |
|
| 2016 |
Qvist S, Greenspan E. Design Space Analysis for Breed-and-Burn Reactor Cores Nuclear Science and Engineering. 182: 197-212. DOI: 10.13182/Nse14-135 |
0.828 |
|
| 2016 |
Hou J, Qvist S, Kellogg R, Greenspan E. 3D in-core fuel management optimization for breed-and-burn reactors Progress in Nuclear Energy. 88: 58-74. DOI: 10.1016/J.Pnucene.2015.12.002 |
0.807 |
|
| 2016 |
Qvist SA, Hellesen C, Thiele R, Dubberley AE, Gradecka M, Greenspan E. Autonomous Reactivity Control (ARC) — Principles, geometry and design process Nuclear Engineering and Design. 307: 249-274. DOI: 10.1016/J.Nucengdes.2016.07.018 |
0.816 |
|
| 2015 |
Gorman PM, Vujic JL, Greenspan E. Trade-off studies for the fuel-self-sustaining RBWR-Th core Nuclear Technology. 191: 282-294. DOI: 10.13182/Nt14-106 |
0.51 |
|
| 2015 |
Seifried JE, Greenspan E. Analysis of local void coefficients of reactivity in the reduced-moderation BWR Nuclear Science and Engineering. 181: 82-95. DOI: 10.13182/Nse14-104 |
0.406 |
|
| 2015 |
Di Sanzo C, Vujic J, Greenspan E. Feasibility of Fueling PWRs with Fuel Discharged from Breed and Burn Reactors Energy Procedia. 71: 78-89. DOI: 10.1016/J.Egypro.2014.11.857 |
0.516 |
|
| 2015 |
Seifried JE, Zhang G, Varela CR, Gorman PM, Greenspan E, Vujic JL. Self-sustaining Thorium-fueled Reduced Moderation BWR Feasibility Study Energy Procedia. 71: 69-77. DOI: 10.1016/J.Egypro.2014.11.856 |
0.592 |
|
| 2015 |
Qvist S, Hou J, Greenspan E. Design and performance of 2D and 3D-shuffled breed-and-burn cores Annals of Nuclear Energy. 85: 93-114. DOI: 10.1016/J.Anucene.2015.04.007 |
0.787 |
|
| 2015 |
Suvdantsetseg E, Qvist S, Greenspan E. Preliminary transient analysis of the Autonomous Reactivity Control system for fast reactors Annals of Nuclear Energy. 77: 47-64. DOI: 10.1016/J.Anucene.2014.11.001 |
0.766 |
|
| 2014 |
Zhang G, Greenspan E, Jolodosky A, Vujic J. SFR with once-through depleted uranium breed & burn blanket Progress in Nuclear Energy. DOI: 10.1016/J.Pnucene.2014.07.044 |
0.778 |
|
| 2014 |
Scarlat RO, Laufer MR, Blandford ED, Zweibaum N, Krumwiede DL, Cisneros AT, Andreades C, Forsberg CW, Greenspan E, Hu LW, Peterson PF. Design and licensing strategies for the fluoride-salt-cooled, high-temperature reactor (FHR) technology Progress in Nuclear Energy. DOI: 10.1016/J.Pnucene.2014.07.002 |
0.794 |
|
| 2014 |
Qvist S, Greenspan E. An Autonomous Reactivity Control system for improved fast reactor safety Progress in Nuclear Energy. 77: 32-47. DOI: 10.1016/J.Pnucene.2014.06.003 |
0.792 |
|
| 2014 |
Zweibaum N, Cao G, Cisneros AT, Kelleher B, Laufer MR, Scarlat RO, Seifried JE, Anderson MH, Forsberg CW, Greenspan E, Hu LW, Peterson PF, Sridharan K. Phenomenology, methods and experimental program for fluoride-salt-cooled, high-temperature reactors (FHRs) Progress in Nuclear Energy. 77: 390-405. DOI: 10.1016/J.Pnucene.2014.04.008 |
0.787 |
|
| 2014 |
Qvist S, Greenspan E. The ADOPT code for automated fast reactor core design Annals of Nuclear Energy. 71: 23-36. DOI: 10.1016/J.Anucene.2014.03.013 |
0.81 |
|
| 2014 |
Zhang G, Greenspan E. Feasibility of thorium-hydride fueled sodium-cooled self-sustaining reactors Transactions of the American Nuclear Society. 111: 307-313. |
0.3 |
|
| 2013 |
Heidet F, Greenspan E. Performance of large breed-and-burn core Nuclear Technology. 181: 381-407. DOI: 10.13182/Nt13-A15800 |
0.737 |
|
| 2013 |
Heidet F, Greenspan E. Superprism-sized breed-andburn sodium-cooled core performance Nuclear Technology. 181: 251-273. DOI: 10.13182/Nt13-A15782 |
0.814 |
|
| 2013 |
Qvist S, Greenspan E. Automated breed & burn core design using the ADOPT code International Congress On Advances in Nuclear Power Plants, Icapp 2013: Nuclear Power - a Safe and Sustainable Choice For Green Future, Held With the 28th Kaif/Kns Annual Conference. 531-539. |
0.412 |
|
| 2012 |
Greenspan E. A phased development of breed-and-burn reactors for enhanced nuclear energy sustainability Sustainability. 4: 2745-2764. DOI: 10.3390/Su4102745 |
0.491 |
|
| 2012 |
Heidet F, Greenspan E. Neutron balance analysis for sustainability of breed-and-burn reactors Nuclear Science and Engineering. 171: 13-31. DOI: 10.13182/Nse10-114 |
0.792 |
|
| 2012 |
Cisneros A, Zweibaum N, Di Sanzo C, Cohen J, Greenspan E, Peterson P, Ludwigt B. Feasibility of once through subcritical cores driven by an accelerator spallation neutron source Fusion Science and Technology. 61: 431-435. DOI: 10.13182/Fst12-A13458 |
0.843 |
|
| 2012 |
Heidet F, Greenspan E. Feasibility of lead cooled breed and burn reactors Progress in Nuclear Energy. 54: 75-80. DOI: 10.1016/J.Pnucene.2011.07.011 |
0.784 |
|
| 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 |
0.757 |
|
| 2011 |
Greenspan E, Heidet F. Energy sustainability and economic stability with Breed and Burn reactors Progress in Nuclear Energy. 53: 794-799. DOI: 10.1016/J.Pnucene.2011.05.002 |
0.777 |
|
| 2011 |
Cisneros AT, Greenspan E, Peterson PF. Pebble bed reactor depletion analysis with multiple fuel types Transactions of the American Nuclear Society. 104: 61-62. |
0.791 |
|
| 2010 |
Ganda F, Vujic J, Greenspan E, Leung K. Compact D-D Neutron Source-Driven Subcritical Multiplier and Beam-Shaping Assembly for Boron Neutron Capture Therapy Nuclear Technology. 172: 302-324. DOI: 10.13182/Nt10-A10939 |
0.75 |
|
| 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 |
0.686 |
|
| 2010 |
Ganda F, Greenspan E. Analysis of reactivity coefficients of hydride-fueled PWR cores Nuclear Science and Engineering. 164: 1-32. DOI: 10.13182/Nse08-64 |
0.81 |
|
| 2010 |
Cisneros AT, Greenspan E, Peterson P. Use of thorium blankets in a pebble bed advanced high temperature reactor International Congress On Advances in Nuclear Power Plants 2010, Icapp 2010. 1: 261-270. |
0.81 |
|
| 2010 |
Heidet F, Greenspan E. Breed-and-burn depleted uranium in fast reactors without actinides separation International Conference On the Physics of Reactors 2010, Physor 2010. 2: 1661-1673. |
0.784 |
|
| 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 |
0.735 |
|
| 2009 |
Olander D, Greenspan E, Garkisch HD, Petrovic B. Uranium-zirconium hydride fuel properties Nuclear Engineering and Design. 239: 1406-1424. DOI: 10.1016/J.Nucengdes.2009.04.001 |
0.509 |
|
| 2009 |
Ganda F, Greenspan E. Plutonium recycling in hydride fueled PWR cores Nuclear Engineering and Design. 239: 1489-1504. DOI: 10.1016/J.Nucengdes.2009.02.025 |
0.807 |
|
| 2009 |
Ganda F, Shuffler C, Greenspan E, Todreas N. Economic analysis of hydride fueled BWR Nuclear Engineering and Design. 239: 1560-1570. DOI: 10.1016/J.Nucengdes.2009.02.024 |
0.766 |
|
| 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 |
0.773 |
|
| 2009 |
Ganda F, Greenspan E. Neutronic analysis of hydride fueled PWR cores Nuclear Engineering and Design. 239: 1425-1441. DOI: 10.1016/J.Nucengdes.2008.12.027 |
0.815 |
|
| 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 |
0.843 |
|
| 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. |
0.618 |
|
| 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 |
0.719 |
|
| 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 |
0.75 |
|
| 2008 |
Susplugas A, Greenspan E. ENHS reactor power level enhancement possibilities Progress in Nuclear Energy. 50: 279-285. DOI: 10.1016/J.Pnucene.2007.11.001 |
0.445 |
|
| 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 |
0.753 |
|
| 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. |
0.722 |
|
| 2008 |
Ganda F, Greenspan E. Plutonium and minor actinides multi-recycling in PWR using hydride fuels International Conference On the Physics of Reactors 2008, Physor 08. 3: 2124-2132. |
0.785 |
|
| 2007 |
Okawa T, Greenspan E. Feasibility of designing the encapsulated nuclear heat source reactor with negative void reactivity feedback Nuclear Technology. 160: 257-278. DOI: 10.13182/Nt07-A3898 |
0.471 |
|
| 2007 |
Ahn J, Cheon M, Greenspan E. Effects of accelerator-driven transmutation system on radiotoxicity of high-level radioactive wastes Nuclear Technology. 158: 408-430. DOI: 10.13182/Nt07-A3851 |
0.481 |
|
| 2007 |
Greenspan E. Hydride fuel for improving the design and performance of LWR Acs National Meeting Book of Abstracts. |
0.441 |
|
| 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. |
0.715 |
|
| 2006 |
Okawa T, Greenspan E. Effect of fuel type on the attainable power of the encapsulated nuclear heat source reactor Proceedings of the 2006 International Congress On Advances in Nuclear Power Plants, Icapp'06. 2006: 415-423. |
0.427 |
|
| 2006 |
Fratoni M, Greenspan E. Optimal hydride fueled BWR assembly designs Physor-2006 - American Nuclear Society's Topical Meeting On Reactor Physics. 2006. |
0.744 |
|
| 2006 |
Ganda F, Greenspan E. Physics of hydride fueled PWR Physor-2006 - American Nuclear Society's Topical Meeting On Reactor Physics. 2006. |
0.784 |
|
| 2005 |
Nishi Y, Ueda N, Kinoshita I, Greenspan E. Computational Analysis of the Thermal-Hydraulic Characteristics of the Encapsulated Nuclear Heat Source Nuclear Technology. 152: 324-338. DOI: 10.13182/Nt05-A3680 |
0.411 |
|
| 2005 |
Greenspan E, Hejzlar P, Sekimoto H, Toshinsky G, Wade D. New fuel cycle and fuel management options in heavy liquid metal-cooled reactors Nuclear Technology. 151: 177-191. DOI: 10.13182/Nt05-A3642 |
0.543 |
|
| 2005 |
Hong SG, Greenspan E, Kim YI. The encapsulated nuclear heat source (ENHS) reactor core design Nuclear Technology. 149: 22-48. DOI: 10.13182/Nt05-A3577 |
0.517 |
|
| 2005 |
Hong SG, Greenspan E. Molten salt cooled Encapsulated Nuclear Heat Source (ENHS)-like reactors Progress in Nuclear Energy. 47: 239-250. DOI: 10.1016/J.Pnucene.2005.05.024 |
0.508 |
|
| 2005 |
Hong SG, Greenspan E. Power flattening options for the ENHS (encapsulated nuclear heat source) core Progress in Nuclear Energy. 47: 178-189. DOI: 10.1016/J.Pnucene.2005.05.018 |
0.478 |
|
| 2005 |
Ganda F, Greenspan E. Incineration of plutonium in PWR using hydride fuel Proceedings of the American Nuclear Society - International Congress On Advances in Nuclear Power Plants 2005, Icapp'05. 6: 3175-3186. |
0.79 |
|
| 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. |
0.635 |
|
| 2004 |
Shayer Z, Greenspan E. Physics characteristics of U-ZrH 1.6 fueled PWR cores Proceedings of the Physor 2004: the Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. 689-696. |
0.449 |
|
| 2004 |
Greenspan E. Generation-IV reactors and nuclear waste minimization Abstracts of the Pacific Basin Nuclear Conference. 61. |
0.444 |
|
| 2004 |
Shayer Z, Greenspan E. Preliminary assessment of possibilities for improving the performance of SCWR using hydride fuel Transactions of the American Nuclear Society. 90: 40-42. |
0.305 |
|
| 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. |
0.674 |
|
| 2003 |
Milošević M, Greenspan E, Vujić JL. Monte Carlo with fuel burnup method for the ENHS benchmark calculations Nuclear Technology & Radiation Protection. 18: 3-11. DOI: 10.2298/Ntrp0302003M |
0.408 |
|
| 2002 |
Greenspan E. The encapsulated nuclear heat source reactor for low-waste proliferation-resistant nuclear energy Progress in Nuclear Energy. 40: 431-439. DOI: 10.1016/S0149-1970(02)00035-5 |
0.489 |
|
| 2001 |
Cheon M, Ahn J, Greenspan E, Chambré PL. Analysis of waste composition from ATW fuel cycle: Lead-bismuth eutectic (LBE) cooled fast reactor Transactions of the American Nuclear Society. 85: 500. |
0.44 |
|
| 2000 |
Ahn J, Greenspan E, Chambré PL. A preliminary consideration for underground autocatalytic criticality by vitrified high-level waste in water-saturated geologic repository Journal of Nuclear Science and Technology. 37: 465-476. DOI: 10.1080/18811248.2000.9714919 |
0.366 |
|
| 1998 |
Vujic J, Greenspan E. Neutronic Analysis of Critical Configurations in Geologic Repositories—II: Highly Enriched Uranium Nuclear Science and Engineering. 129: 1-14. DOI: 10.13182/Nse98-A1960 |
0.324 |
|
| 1997 |
Greenspan E, Vujic J, Burch J. Neutronic Analysis of Critical Configurations in Geologic Repositories: I - Weapons-Grade Plutonium Nuclear Science and Engineering. 127: 262-291. DOI: 10.13182/Nse97-A1935 |
0.321 |
|
| 1996 |
Kastenberg WE, Peterson PF, Ahn J, Burch J, Casher G, Chambré PL, Greenspan E, Olander DR, Vujic JL, Bessinger B, Cook NGW, Doyle FM, Hilbert LB. Considerations of autocatalytic criticality of fissile materials in geologic repositories Nuclear Technology. 115: 298-309. DOI: 10.13182/Nt96-2 |
0.345 |
|
| 1996 |
Greenspan E. Advances in neutronic capability for fusion reactor design optimization Fusion Technology. 30: 1069-1075. DOI: 10.13182/Fst96-A11963092 |
0.355 |
|
| 1995 |
Greenspan E, Annese CE, Miller WF, Watkins EF, Tobin ML, Latkowski JF, Lee JD, Soran P. Efficient Time-Independent Method for Conceptual Design Optimization of the National Ignition Facility Primary Shield Fusion Technology. 27: 417-451. DOI: 10.13182/Fst95-A30362 |
0.351 |
|
| 1993 |
Ho SK, Annese C, Fowler TK, Greenspan E, Holdren JP, Levinson R, Lowenthal MD, Sarigiannis DA. Integrated fusion environmental and safety systems studies Journal of Fusion Energy. 12: 163-169. DOI: 10.1007/Bf01059373 |
0.311 |
|
| 1986 |
Greenspan E. Fusion reactors blanket nucleonics Progress in Nuclear Energy. 17: 53-139. DOI: 10.1016/0149-1970(86)90042-9 |
0.392 |
|
| 1985 |
Greenspan E. Fusion Reactors for Co-Generation of Fissile Fuel and 3He Fusion Technology. 7: 437-437. DOI: 10.13182/Fst85-A24565 |
0.463 |
|
| 1984 |
Greenspan E. FUSION-FISSION HYBRID REACTORS Advances in Nuclear Science and Technology. 16: 289-515. |
0.326 |
|
| 1984 |
Jung J, Greenspan E, Miley GH. BLANKETS FOR TRITIUM CATALYZED DEUTERIUM FUSION REACTORS Transactions of the American Nuclear Society. 46: 232-233. |
0.319 |
|
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