| Year |
Citation |
Score |
| 2020 |
Zweibaum N, Blandford E, Gerardi C, Peterson P. Scaling Methodology for Integral Effects Tests in Support of Fluoride Salt–Cooled High-Temperature Reactor Technology Nuclear Science and Engineering. 194: 793-811. DOI: 10.1080/00295639.2019.1710976 |
0.688 |
|
| 2020 |
Blandford E, Brumback K, Fick L, Gerardi C, Haugh B, Hillstrom E, Johnson K, Peterson PF, Rubio F, Sarikurt FS, Sen S, Zhao H, Zweibaum N. Kairos power thermal hydraulics research and development Nuclear Engineering and Design. 364: 110636. DOI: 10.1016/J.Nucengdes.2020.110636 |
0.76 |
|
| 2020 |
Liu L, Peterson P, Zhang D, Johnson I, Qiu S, Su G. Scaling and distortion analysis using a simple natural circulation loop for FHR development Applied Thermal Engineering. 168: 114849. DOI: 10.1016/J.Applthermaleng.2019.114849 |
0.327 |
|
| 2019 |
Omair Z, Scranton G, Pazos-Outón LM, Xiao TP, Steiner MA, Ganapati V, Peterson PF, Holzrichter J, Atwater H, Yablonovitch E. Ultraefficient thermophotovoltaic power conversion by band-edge spectral filtering. Proceedings of the National Academy of Sciences of the United States of America. PMID 31311864 DOI: 10.1073/Pnas.1903001116 |
0.32 |
|
| 2019 |
Forsberg CW, Peterson PF. FHR, HTGR, and MSR Pebble-Bed Reactors with Multiple Pebble Sizes for Fuel Management and Coolant Cleanup Nuclear Technology. 205: 748-754. DOI: 10.1080/00295450.2019.1573619 |
0.401 |
|
| 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 |
0.792 |
|
| 2018 |
Bardet PM, Peterson PF, Savaş Ö. Annular swirling liquid layer with a hollow core Journal of Fluid Mechanics. 841: 784-824. DOI: 10.1017/Jfm.2018.76 |
0.664 |
|
| 2018 |
Huddar L, Kendrick JC, Poresky C, Wang X, Peterson PF. Application of frequency response methods in separate and integral effects tests for molten salt cooled and fueled reactors Nuclear Engineering and Design. 329: 3-11. DOI: 10.1016/J.Nucengdes.2017.11.045 |
0.398 |
|
| 2017 |
Andreades C, Peterson P. Nuclear Air Brayton Combined Cycle and Mark 1 Pebble Bed Fluoride-Salt-Cooled High-Temperature Reactor economic performance in a regulated electricity market Nuclear Engineering and Design. 323: 474-484. DOI: 10.1016/J.Nucengdes.2016.12.013 |
0.327 |
|
| 2016 |
Forsberg C, Peterson PF. Basis for fluoride salt-cooled high-temperature reactors with nuclear air-brayton combined cycles and firebrick resistance-heated energy storage Nuclear Technology. 196: 13-33. DOI: 10.13182/Nt16-28 |
0.44 |
|
| 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, ... ... Peterson P, 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 |
0.792 |
|
| 2016 |
Zweibaum N, Guo Z, Kendrick JC, Peterson PF. Design of the Compact Integral Effects Test Facility and Validation of Best-Estimate Models for Fluoride Salt–Cooled High-Temperature Reactors Nuclear Technology. 196: 641-660. DOI: 10.13182/Nt16-15 |
0.432 |
|
| 2016 |
Guo Z, Zweibaum N, Shao M, Huddar LR, Peterson PF, Qiu S. Development of the FHR advanced natural circulation analysis code and application to FHR safety analysis Progress in Nuclear Energy. 91: 56-67. DOI: 10.1016/J.Pnucene.2016.03.022 |
0.405 |
|
| 2016 |
Buster GC, Laufer MR, Peterson PF. A scaled experimental study of control blade insertion dynamics in Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactors Nuclear Engineering and Design. 303: 153-162. DOI: 10.1016/J.Nucengdes.2016.04.015 |
0.605 |
|
| 2015 |
Forsberg C, Peterson PF. Spent nuclear fuel and graphite management for salt-cooled reactors: Storage, safeguards, and repository disposal Nuclear Technology. 191: 113-121. DOI: 10.13182/Nt14-88 |
0.393 |
|
| 2015 |
Zweibaum N, Bickel JE, Guo Z, Kendrick JC, Peterson PF. Design, fabrication and startup testing in the compact integral effects test facility in support of fluoride-salt-cooled, high-temperature reactor technology International Topical Meeting On Nuclear Reactor Thermal Hydraulics 2015, Nureth 2015. 2: 1688-1703. |
0.318 |
|
| 2015 |
Huddar L, Peterson PF, Scarlat R, Guo Z. Experimental strategy for the determination of heat transfer coefficients in pebble-beds cooled by fluoride salts International Topical Meeting On Nuclear Reactor Thermal Hydraulics 2015, Nureth 2015. 2: 1659-1675. |
0.662 |
|
| 2015 |
Haneklaus N, Kendrick J, Huddar L, Zweibaum N, Peterson PF, Hughes J, Blandford E, Lv Q, Sun X, Yoder G. Thermal hydraulic benchmarking exercises to support fluoride-salt-cooled, high-temperature reactor (FHR) licensing International Topical Meeting On Nuclear Reactor Thermal Hydraulics 2015, Nureth 2015. 8: 6918-6930. |
0.641 |
|
| 2014 |
Andreades C, Dempsey L, Peterson PF. Reheat air-brayton combined cycle power conversion off-nominal and transient performance Journal of Engineering For Gas Turbines and Power. 136. DOI: 10.1115/1.4026612 |
0.398 |
|
| 2014 |
Andreades C, Scarlat RO, Dempsey L, Peterson P. Reheat-air brayton combined cycle power conversion design and performance under nominal ambient conditions Journal of Engineering For Gas Turbines and Power. 136. DOI: 10.1115/1.4026506 |
0.738 |
|
| 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 |
0.814 |
|
| 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 |
0.798 |
|
| 2014 |
Scarlat RO, Peterson PF. The current status of fluoride salt cooled high temperature reactor (FHR) technology and its overlap with HIF target chamber concepts Nuclear Instruments and Methods in Physics Research, Section a: Accelerators, Spectrometers, Detectors and Associated Equipment. 733: 57-64. DOI: 10.1016/J.Nima.2013.05.094 |
0.768 |
|
| 2014 |
Krumwiede DL, Andreades C, Choi JK, Cisneros AT, Huddar L, Huff KD, Laufer MR, Munk M, Scarlat RO, Seiffied JE, Zweibaum N, Greenspan E, Peterson PF. Design of the Mark-I pebble-bed, fluoride-salt-cooled, high-temperature reactor commercial power plant International Congress On Advances in Nuclear Power Plants, Icapp 2014. 1: 413-422. |
0.798 |
|
| 2014 |
Guo Z, Scarlat RO, Huddar L, Zweibaum N, Peterson PF, Qiu S, Su G. Verification and validation of a natural circulation loop model for FHRs Embedded Topical Meeting On Advances in Thermal Hydraulics, Ath 2014, Held At the American Nuclear Society 2014 Annual Meeting. 227-246. |
0.699 |
|
| 2013 |
Urquiza E, Lee K, Peterson PF, Greif R. Multiscale transient thermal, hydraulic, and mechanical analysis methodology of a printed circuit heat exchanger using an effective porous media approach Journal of Thermal Science and Engineering Applications. 5. DOI: 10.1115/1.4024712 |
0.801 |
|
| 2013 |
Blandford ED, Peterson PF. A buoyantly-driven shutdown rod concept for passive reactivity control of a Fluoride salt-cooled High-temperature Reactor Nuclear Engineering and Design. 262: 600-610. DOI: 10.1016/J.Nucengdes.2013.05.025 |
0.724 |
|
| 2013 |
Krumwiede DL, Scarlat RO, Choi JK, Phan TM, Peterson PF. Three-dimensional modeling of the pebble-bed fluoride-salt-cooled, high-temperature reactor (PB-FHR) commercial plant design Transactions of the American Nuclear Society. 109: 287-290. |
0.702 |
|
| 2013 |
Scarlat RO, Zweibaum N, Huddar L, Peterson PF. The role of modeling and scaled experiments in advanced nuclear reactor design and safety analysis Nuclear Engineering Division 2013 - Core Programming Area At the 2013 Aiche Annual Meeting: Global Challenges For Engineering a Sustainable Future. 15. |
0.67 |
|
| 2013 |
Scarlat RO, Zweibaum N, Peterson PF. Phenomena identification and ranking matrix (PIRM) for the pebble bed fluoride-salt-cooled, high-temperature reactor (PB-FHR) Transactions of the American Nuclear Society. 109: 1770-1773. |
0.675 |
|
| 2013 |
Huddar L, Scarlat RO, Zweibaum N, Peterson PF, Krumwiede D. Overview of passive safety features and transient model validation for the pebble-bed fluoride-salt cooled, high-temperature nuclear reactor (PB-FHR) Nuclear Engineering Division 2013 - Core Programming Area At the 2013 Aiche Annual Meeting: Global Challenges For Engineering a Sustainable Future. 7. |
0.687 |
|
| 2013 |
Andreaes C, Scarlat RO, Peterson PF. Combined cycle power conversion with natural gas co-firing, for the pebble-bed fluoride-salt cooled, high-temperature nuclear reactor (PB-FHR) Nuclear Engineering Division 2013 - Core Programming Area At the 2013 Aiche Annual Meeting: Global Challenges For Engineering a Sustainable Future. 16-17. |
0.697 |
|
| 2013 |
Zweibaum N, Scarlat RO, Peterson PF. Design of a compact integral effects test facility for fluoride-salt- cooled, high-temperature reactors Transactions of the American Nuclear Society. 109: 1588-1591. |
0.704 |
|
| 2013 |
Scarlat RO, Huddar L, Peterson PF. Overview of the pebble-bed fluoride-salt-cooled, high-temperature nuclear reactor (PB-FHR) and management of tritium air emissions Nuclear Engineering Division 2013 - Core Programming Area At the 2013 Aiche Annual Meeting: Global Challenges For Engineering a Sustainable Future. 6. |
0.666 |
|
| 2012 |
Peterson PF. Elements of the proliferation resistance and physical protection evaluation methodology Nuclear Technology. 179: 45-51. DOI: 10.13182/Nt179-45 |
0.319 |
|
| 2012 |
Zhao H, Peterson PF. Advanced multieffect distillation system for desalination using waste heat from gas Brayton cycles Nuclear Technology. 180: 422-436. DOI: 10.13182/Nt12-A15353 |
0.594 |
|
| 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 |
0.375 |
|
| 2012 |
Scarlat RO, Cisneros AT, Koutchesfahani T, Hong R, Peterson PF. Preliminary safety analysis of a PBMR supplying process heat to a co-located ethylene production plant Nuclear Engineering and Design. 251: 53-59. DOI: 10.1016/J.Nucengdes.2011.10.069 |
0.717 |
|
| 2012 |
Blandford ED, Forsberg CW, Peterson PF. Passive decay heat removal strategies for the fluoride salt-cooled high-temperature reactor (FHR) Transactions of the American Nuclear Society. 107: 915-918. |
0.667 |
|
| 2012 |
Blandford ED, Laufer MR, Peterson PF. Development of risk metrics for the fluoride salt-cooled high temperature reactor Transactions of the American Nuclear Society. 107: 911-914. |
0.739 |
|
| 2012 |
Cisneros AT, Scarlat RO, Laufer MR, Greenspan E, Peterson PF. Pebble fuel design for the PB-FHR International Congress On Advances in Nuclear Power Plants 2012, Icapp 2012. 2: 900-910. |
0.771 |
|
| 2011 |
Halecky N, Birkholzer J, Peterson P. Natural convection in tunnels at Yucca Mountain and impact on drift seepage Nuclear Technology. 174: 327-341. DOI: 10.13182/Nt11-A11743 |
0.325 |
|
| 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 |
0.756 |
|
| 2011 |
Schmidt J, Scheiffele M, Crippa M, Peterson PF, Urquiza E, Sridharan K, Olson LC, Anderson MH, Allen TR, Chen Y. Design, fabrication, and testing of ceramic plate-type heat exchangers with integrated flow channel design International Journal of Applied Ceramic Technology. 8: 1073-1086. DOI: 10.1111/J.1744-7402.2010.02573.X |
0.791 |
|
| 2010 |
Bardet PM, Peterson PF, Savaş O. Split-screen single-camera stereoscopic PIV application to a turbulent confined swirling layer with free surface Experiments in Fluids. 49: 513-524. DOI: 10.1007/S00348-010-0823-2 |
0.67 |
|
| 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. |
0.725 |
|
| 2010 |
Borrelli RA, Kim L, Blandford E, Hwang Y, Kim EH, Peterson PF. High reliability safeguards For remote-handled nuclear materials International Congress On Advances in Nuclear Power Plants 2010, Icapp 2010. 3: 1846-1855. |
0.634 |
|
| 2010 |
Bickel JE, Laufer MR, Li L, Cisneros AT, Peterson PF. Conceptual design, experiments, and analysis for the core of an FHR-16 test reactor International Congress On Advances in Nuclear Power Plants 2010, Icapp 2010. 2: 1281-1291. |
0.647 |
|
| 2010 |
Galvez C, Wang R, Margossian S, Dionisio S, Peterson PF. Modeling and transient simulation of the PB-AHTR using RELAP5 International Congress On Advances in Nuclear Power Plants 2010, Icapp 2010. 2: 1499-1509. |
0.313 |
|
| 2009 |
Zhao H, Peterson PF. One-dimensional analysis of thermal stratification in the AHTR coolant pool Nuclear Engineering and Technology. 41: 953-968. DOI: 10.5516/Net.2009.41.7.953 |
0.62 |
|
| 2009 |
Peterson PF, Blandford E, Galvez C. Overview of Fission Safety for Laser ICF Fission Energy Fusion Science and Technology. 56: 641-646. DOI: 10.13182/Fst56-641 |
0.676 |
|
| 2009 |
Abbott RP, Gerhard MA, Kramer KJ, Latkowski JF, Morris KL, Peterson PF, Seifried JE. Thermal and mechanical design aspects of the life engine Fusion Science and Technology. 56: 618-624. DOI: 10.13182/Fst18-8002 |
0.783 |
|
| 2009 |
Moses EI, De La Rubia TD, Storm E, Latkowski JF, Farmer JC, Abbott RP, Kramer KJ, Peterson PF, Shaw HF, Lehman RF. A sustainable nuclear fuel cycle based on laser inertial fusion energy Fusion Science and Technology. 56: 547-565. DOI: 10.13182/Fst09-34 |
0.349 |
|
| 2009 |
Zhao H, Zhang H, Mousseau VA, Peterson PF. Improving SFR economics through innovations from thermal design and analysis aspects Nuclear Engineering and Design. 239: 1042-1055. DOI: 10.1016/J.Nucengdes.2009.02.012 |
0.586 |
|
| 2009 |
Blandford ED, Peterson PF. A novel buoyantly-driven shutdown rod design for passive reactivity control of the PB-AHTR 2008 Proceedings of the 4th International Topical Meeting On High Temperature Reactor Technology, Htr 2008. 2: 255-263. |
0.708 |
|
| 2008 |
Bardet PM, Peterson PF. Options for scaled experiments for high temperature liquid salt and helium fluid mechanics and convective heat transfer Nuclear Technology. 163: 344-357. DOI: 10.13182/Nt163-344 |
0.702 |
|
| 2008 |
Birkholzer JT, Halecky N, Webb SW, Peterson PF, Bodvarsson GS. A modeling study evaluating the thermal-hydrological conditions in and near waste emplacement drifts at Yucca Mountain Nuclear Technology. 163: 147-164. DOI: 10.13182/Nt08-A3978 |
0.363 |
|
| 2008 |
Zhao H, Peterson PF. Multiple reheat helium Brayton cycles for sodium cooled fast reactors Nuclear Engineering and Design. 238: 1535-1546. DOI: 10.1016/J.Nucengdes.2007.12.002 |
0.585 |
|
| 2008 |
Bardet P, Blandford E, Fratoni M, Niquille A, Greenspan E, Peterson PF. Design, analysis and development of the modular PB-AHTR International Conference On Advances in Nuclear Power Plants, Icapp 2008. 1: 161-178. |
0.806 |
|
| 2008 |
Forsberg CW, Peterson PF, Kochendarfer RA. Design options for the advanced high-temperature reactor International Conference On Advances in Nuclear Power Plants, Icapp 2008. 2: 733-749. |
0.349 |
|
| 2007 |
Zhao H, Peterson PF. Optimization of advanced high-temperature Brayton cycles with multiple-reheat stages Nuclear Technology. 158: 145-157. DOI: 10.13182/Nt07-A3832 |
0.627 |
|
| 2007 |
De Losier CR, Subramanian S, Ponyavin V, Chen Y, Hechanova AE, Peterson PF. The parametric study of an innovative offset strip-fin heat exchanger Journal of Heat Transfer. 129: 1453-1458. DOI: 10.1115/1.2755068 |
0.343 |
|
| 2007 |
Forsberg CW, Peterson PF, Zhao H. High-temperature liquid-fluoride-salt closed-brayton-cycle solar power towers Journal of Solar Energy Engineering, Transactions of the Asme. 129: 141-146. DOI: 10.1115/1.2710245 |
0.617 |
|
| 2007 |
Niu F, Zhao H, Peterson PF, Woodcock J, Henry RE. Investigation of mixed convection in a large rectangular enclosure Nuclear Engineering and Design. 237: 1025-1032. DOI: 10.1016/J.Nucengdes.2006.12.011 |
0.595 |
|
| 2007 |
Fukuda GT, Peterson PF, Olander DR, Prausnitz JM. Thermodynamics of the LiF-NaF-BeF2 system at high temperatures Fluid Phase Equilibria. 255: 1-10. DOI: 10.1016/J.Fluid.2007.01.041 |
0.797 |
|
| 2007 |
Debonnel CS, Trubov L, Zeballos CA, Peterson PF. The multi-physics, user-friendly gas-dynamics code Visual Tsunami 2.0 Joint International Topical Meeting On Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + Sna 2007. |
0.753 |
|
| 2007 |
Griveau A, Fardin F, Zhao H, Peterson PF. Transient thermal response of the PB-AHTR to loss of forced cooling Global 2007: Advanced Nuclear Fuel Cycles and Systems. 872-884. |
0.302 |
|
| 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. |
0.309 |
|
| 2007 |
Zhao H, Peterson PF. One-dimensional analysis of thermal stratification in AHTR and SFR coolant pools Proceedings - 12th International Topical Meeting On Nuclear Reactor Thermal Hydraulics, Nureth-12. |
0.328 |
|
| 2007 |
Bardet P, An JY, Franklin JT, Huang D, Lee K, Mai A, Toulouse M, Peterson PF. The Pebble Recirculation Experiment (PREX) for the AHTR Global 2007: Advanced Nuclear Fuel Cycles and Systems. 845-851. |
0.711 |
|
| 2007 |
Bardet PM, Abbott RP, Campen C, Franklin J, Haihua Z, Peterson PF. Experimental investigation of Z-pinch IFE chamber liquid structure response Fusion Science and Technology. 52: 932-937. |
0.701 |
|
| 2006 |
Logan G, Lee E, Yu S, Briggs D, Barnard J, Friedman A, Qin H, Waldron W, Leitner M, Kwan J, Henestroza E, Caporaso G, Meier W, Tabak M, Callahan D, ... ... Peterson P, et al. What product might a renewal of Heavy IonFusion development offerthat competes with methane microbes and hydrogen HTGRs Lawrence Berkeley National Laboratory. DOI: 10.2172/902800 |
0.343 |
|
| 2006 |
Birkholzer JT, Webb SW, Halecky N, Peterson PF, Bodvarsson GS. Evaluating the moisture conditions in the fractured rock at Yucca Mountain: The impact of natural convection processes in heated emplacement drifts Vadose Zone Journal. 5: 1172-1193. DOI: 10.2136/Vzj2005.0147 |
0.326 |
|
| 2006 |
Raffray AR, Meier W, Abdel-Khalik S, Bonazza R, Calderoni P, Debonnel CS, Dragojlovic Z, El-Guebaly L, Haynes D, Latkowski J, Olson C, Peterson PF, Reyes S, Sharpe P, Tillack MS, et al. IFE thick liquid wall chamber dynamics: Governing mechanisms and modeling and experimental capabilities Fusion Science and Technology. 49: 1-27. DOI: 10.13182/Fst06-A1082 |
0.797 |
|
| 2006 |
Forsberg CW, Peterson PF, Cahalan JE, Enneking JA, MacDonald P. Refueling liquid-salt-cooled very high-temperature reactors International Conference On Nuclear Engineering, Proceedings, Icone. 2006. DOI: 10.1115/ICONE14-89471 |
0.363 |
|
| 2006 |
Fukuda GT, Peterson PF, Olander DR. Vapor pressure measurements on mixtures of LiF, NaF, and BeF 2 Proceedings - Symposium On Fusion Engineering. DOI: 10.1109/FUSION.2005.252917 |
0.779 |
|
| 2006 |
Forsberg CW, Peterson PF, Zhao H. Sustainability and economics of the advanced high-temperature reactor Journal of Energy Engineering. 132: 109-115. DOI: 10.1061/(Asce)0733-9402(2006)132:3(109) |
0.581 |
|
| 2006 |
Peterson PF, Zhao H. A flexible baseline design for the Advanced High Temperature Reactor using Metallic Internals (AHTR-MI) Proceedings of the 2006 International Congress On Advances in Nuclear Power Plants, Icapp'06. 2006: 650-661. |
0.364 |
|
| 2005 |
Bardet PM, Supiot BF, Peterson PF, Savaş O. Liquid vortex shielding for fusion energy applications Fusion Science and Technology. 47: 1192-1196. DOI: 10.13182/Fst05-A849 |
0.71 |
|
| 2005 |
Debonnel CS, Wang TX, Suzuki M, Garcia E, Peterson PF. Visual TSUNAMI: A versatile, user-friendly, multidimensional ablation and gas-dynamics design code Fusion Science and Technology. 47: 1165-1169. DOI: 10.13182/Fst05-A844 |
0.787 |
|
| 2005 |
Olson C, Rochau G, Slutz S, Morrow C, Olson R, Cuneo M, Hanson D, Bennett G, Sanford T, Bailey J, Stygar W, Vesey R, Mehlhorn T, Struve K, Mazarakis M, ... ... Peterson P, et al. Development Path for Z-Pinch IFE Fusion Science and Technology. 47: 633-640. DOI: 10.13182/Fst05-A757 |
0.335 |
|
| 2005 |
Bardet PM, Debonnel CS, Freeman J, Fukuda G, Supiot B, Peterson PF. Dynamics of liquid-protected fusion chambers Fusion Science and Technology. 47: 626-632. DOI: 10.13182/Fst05-A756 |
0.796 |
|
| 2005 |
Yu SS, Barnard JJ, Briggs RJ, Callahan-Miller D, Chao LL, Davidson R, Debonnel CS, Eylon S, Friedman A, Henestroza E, Kaganovich I, Kwan JW, Lee EP, Leitner M, Logan BG, ... ... Peterson PF, et al. Towards a modular point design for heavy ion fusion Fusion Science and Technology. 47: 621-625. DOI: 10.13182/Fst05-A755 |
0.793 |
|
| 2005 |
Wong CPC, Malang S, Sawan M, Smolentsev S, Majumdar S, Merrill B, Sze DK, Morley N, Sharafat S, Dagher M, Peterson P, Zhao H, Zinkle SJ, Abdou M, Youssef M. Assessment of first wall and blanket options with the use of liquid breeder Fusion Science and Technology. 47: 502-509. DOI: 10.13182/Fst05-A734 |
0.637 |
|
| 2005 |
Zhao H, Fukuda G, Abbott RP, Peterson PF. Optimized helium-brayton power conversion for fusion energy systems Fusion Science and Technology. 47: 460-466. DOI: 10.13182/Fst05-A730 |
0.802 |
|
| 2005 |
Debonnel CS, Yu SS, Peterson PF. Progress towards thick liquid fusion chambers for assisted-pinch and solenoid focusings Nuclear Instruments and Methods in Physics Research, Section a: Accelerators, Spectrometers, Detectors and Associated Equipment. 544: 342-346. DOI: 10.1016/J.Nima.2005.01.231 |
0.802 |
|
| 2005 |
Yu SS, Abbott RP, Bangerter RO, Barnard JJ, Briggs RJ, Callahan D, Celata CM, Davidson R, Debonnel CS, Eylon S, Faltens A, Friedman A, Grote DP, Heitzenroeder P, Henestroza E, ... ... Peterson PF, et al. Heavy ion fusion (HIF) driver point designs Nuclear Instruments and Methods in Physics Research, Section a: Accelerators, Spectrometers, Detectors and Associated Equipment. 544: 294-299. DOI: 10.1016/J.Nima.2005.01.223 |
0.786 |
|
| 2005 |
Laurenty B, Fukuda G, Damba DD, Mai A, Peterson PF. Inhibiting corrosion in Molten fluoride salts: Investigation on Flinak Aiche Annual Meeting, Conference Proceedings. 7878-7882. |
0.751 |
|
| 2005 |
Forsberg CW, Peterson PF, Williams DF. Practical aspects of liquid-salt-cooled fast-neutron reactors Proceedings of the American Nuclear Society - International Congress On Advances in Nuclear Power Plants 2005, Icapp'05. 6: 3197-3209. |
0.31 |
|
| 2005 |
Forsberg CW, Peterson PF, Williams DF. Liquid-salt cooling for Advanced High-Temperature Reactors Proceedings of the American Nuclear Society - International Congress On Advances in Nuclear Power Plants 2005, Icapp'05. 4: 2080-2095. |
0.349 |
|
| 2004 |
Forsberg C, Peterson PF, Pickard PS. Advanced CSiC Composites for High-temperature Nuclear Heat Transport with Helium, Molten Salts, and Sulphur-iodine Thermochemical Hydrogen Process Fluids Nuclear Science. 289-302. DOI: 10.1787/9789264107717-23-En |
0.394 |
|
| 2004 |
Senn SM, Pemberton SJ, Peterson PF. Nonsinusoidal nozzle oscillation functions for generating thick-liquid pockets for heavy-ion fusion chambers Fusion Science and Technology. 45: 573-582. DOI: 10.13182/Fst04-A532 |
0.781 |
|
| 2004 |
Sharp WM, Callahan DA, Tabak M, Yu SS, Peterson PF, Rose DV, Welch DR. Chamber-transport simulation results for heavy-ion fusion drivers Nuclear Fusion. 44: S221-S227. DOI: 10.1088/0029-5515/44/12/S13 |
0.339 |
|
| 2004 |
Forsberg CW, Peterson PF, Pickard P. Maximizing temperatures of delivered heat from the advanced high-temperature reactor Proceedings of the 2004 International Congress On Advances in Nuclear Power Plants, Icapp'04. 321-331. |
0.318 |
|
| 2003 |
Peterson PF. Multiple-reheat Brayton cycles for nuclear power conversion with molten coolants Nuclear Technology. 144: 279-288. DOI: 10.13182/Nt144-279 |
0.388 |
|
| 2003 |
Forsberg CW, Peterson PF, Pickard PS. Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity Nuclear Technology. 144: 289-302. DOI: 10.13182/Nt03-1 |
0.435 |
|
| 2003 |
Pemberton SJ, Abbott RP, Peterson PF. Thick-liquid blanket configuration and response for the HIF point design Fusion Science and Technology. 44: 294-299. DOI: 10.13182/Fst03-A350 |
0.805 |
|
| 2003 |
Debonnel CS, Yu SS, Peterson PF. X-ray ablation and debris venting for the HIF point design Fusion Science and Technology. 44: 274-278. DOI: 10.13182/Fst03-A346 |
0.807 |
|
| 2003 |
Yu SS, Meier WR, Abbott RP, Barnard JJ, Brown T, Callahan DA, Heitzenroeder P, Latkowski JF, Logan BG, Pemberton SJ, Peterson PF, Rose DV, Sabbi G-, Sharp WM, Welch DR. An Updated Point Design for Heavy Ion Fusion Fusion Science and Technology. 44: 266-273. DOI: 10.13182/Fst03-A345 |
0.799 |
|
| 2003 |
Debonnel CS, Welch DR, Rose DV, Yu SS, Peterson PF. Gas transport and density control in the HYLIFE heavy-ion beam lines Fusion Science and Technology. 43: 408-413. DOI: 10.13182/Fst03-A285 |
0.789 |
|
| 2003 |
Pemberton SJ, Abbott RP, Peterson PF. Annular vortex generation for inertial fusion energy beam-line protection Fusion Science and Technology. 43: 378-383. DOI: 10.13182/Fst03-A281 |
0.79 |
|
| 2003 |
Sharp WM, Callahan DA, Tabak M, Yu SS, Peterson PF. Chamber transport of "foot" pulses for heavy-ion fusion Physics of Plasmas. 10: 2457-2467. DOI: 10.1063/1.1570826 |
0.315 |
|
| 2003 |
Yu SS, Meier WR, Abbott RP, Barnard JJ, Brown T, Callahan DA, Debonnel C, Heitzenroeder P, Latkowski JF, Logan BG, Pemberton SJ, Peterson PF, Rose DV, Sabbi GL, Sharp WM, et al. An updated point design for heavy ion fusion Fusion Science and Technology. 44: 266-273. |
0.789 |
|
| 2002 |
Kuhn SZ, Kang HK, Peterson PF. Study of mixing and augmentation of natural convection heat transfer by a forced jet in a large enclosure Journal of Heat Transfer. 124: 660-666. DOI: 10.1115/1.1482081 |
0.32 |
|
| 2002 |
Meier WR, Logan BG, Waldron WL, Sabbi GL, Callahan DA, Peterson PF, Goodin DT. Progress toward heavy-ion IFE Fusion Engineering and Design. 63: 577-585. DOI: 10.1016/S0920-3796(02)00273-9 |
0.415 |
|
| 2002 |
Debonnel CS, Fukuda GT, Bardet PM, Peterson PF. Control of the heavy-ion beam line gas pressure and density in the HYLIFE thick-liquid chamber Fusion Engineering and Design. 63: 647-652. DOI: 10.1016/S0920-3796(02)00140-0 |
0.777 |
|
| 2002 |
Pemberton SJ, Abbott RP, Peterson PF. Abatement of shocks during disruption of porous thick-liquid blankets in HYLIFE-type inertial fusion chambers Fusion Engineering and Design. 63: 641-646. DOI: 10.1016/S0920-3796(02)00139-4 |
0.792 |
|
| 2001 |
Peterson PF. The pros and cons of nuclear fuel recycling. Science (New York, N.Y.). 294: 2093-4. PMID 11764789 DOI: 10.1126/Science.294.5549.2093C |
0.331 |
|
| 2001 |
Woodcock J, Peterson PF, Spencer DR. Quantifying the Effects of Break Source Flow Rates on AP600 Containment Stratification Nuclear Technology. 134: 37-48. DOI: 10.13182/Nt01-A3184 |
0.363 |
|
| 2001 |
Abbott R, Pemberton S, Peterson PF, Sun GP, Wright P, Holmes R, Latkowski J, Moir R, Springer K. Cylindrical liquid jet grids for beam-port protection of thick-liquid heavy-ion fusion target chambers Fusion Technology. 39: 732-738. DOI: 10.13182/Fst01-A11963326 |
0.789 |
|
| 2001 |
Peterson PF. Design methods for thick-liquid protection of inertial fusion chambers Fusion Technology. 39: 702-710. DOI: 10.13182/Fst01-A11963321 |
0.438 |
|
| 2001 |
Jantzen C, Peterson PF. Scaled impulse loading for liquid hydraulic response in IFE thick-liquid chamber experiments Nuclear Instruments and Methods in Physics Research, Section a: Accelerators, Spectrometers, Detectors and Associated Equipment. 464: 404-409. DOI: 10.1016/S0168-9002(01)00076-6 |
0.373 |
|
| 2001 |
Bauman C, Pemberton S, Peterson PF. Single-jet experiments for HIF thick-liquid chambers Nuclear Instruments and Methods in Physics Research, Section a: Accelerators, Spectrometers, Detectors and Associated Equipment. 464: 400-403. DOI: 10.1016/S0168-9002(01)00075-4 |
0.788 |
|
| 2001 |
Peterson PF. HIF liquid hydraulics scaling and pocket design Nuclear Instruments and Methods in Physics Research, Section a: Accelerators, Spectrometers, Detectors and Associated Equipment. 464: 159-164. DOI: 10.1016/S0168-9002(01)00027-4 |
0.426 |
|
| 2001 |
Gamble RE, Nguyen TT, Shiralkar BS, Peterson PF, Greif R, Tabata H. Pressure suppression pool mixing in passive advanced BWR plants Nuclear Engineering and Design. 204: 321-336. DOI: 10.1016/S0029-5493(00)00363-0 |
0.797 |
|
| 2001 |
Kuhn SZ, Bernardis RD, Lee CH, Peterson PF. Density stratification from buoyancy-driven exchange flow through horizontal partitions in a liquid tank Nuclear Engineering and Design. 204: 337-345. DOI: 10.1016/S0029-5493(00)00360-5 |
0.341 |
|
| 2001 |
Christensen J, Peterson PF. A one-dimensional Lagrangian model for large-volume mixing Nuclear Engineering and Design. 204: 299-320. DOI: 10.1016/S0029-5493(00)00327-7 |
0.511 |
|
| 2001 |
Pemberton S, Jantzen C, Kuhn J, Peterson PF. Partial pocket experiments for IFE thick-liquid pocket disruption and clearing Fusion Technology. 39: 726-731. |
0.763 |
|
| 1998 |
Jantzen C, Lee EP, Peterson PF. Parametric Studies of Ablation and Venting from the Central Cavity of the HYLIFE-II Reactor Fusion Technology. 34: 1047-1052. DOI: 10.13182/Fst98-A11963752 |
0.736 |
|
| 1998 |
Peterson PF, Schrock VE, Greif R. Scaling for integral simulation of mixing in large, stratified volumes Nuclear Engineering and Design. 186: 213-224. DOI: 10.1016/S0029-5493(98)00223-4 |
0.341 |
|
| 1997 |
Obonai A, Peterson PF, Schrock VE. Point measurements of noncondensable gas concentration in condensing systems Journal of Heat Transfer. 119: 152-157. DOI: 10.1115/1.2824080 |
0.362 |
|
| 1997 |
Fox RJ, Peterson PF, Corradini ML, Pernsteiner AP. Free convective condensation in a vertical enclosure Nuclear Engineering and Design. 177: 71-89. DOI: 10.1016/S0029-5493(97)00186-6 |
0.353 |
|
| 1997 |
Kuhn SZ, Schrock VE, Peterson PF. An investigation of condensation from steam-gas mixtures flowing downward inside a vertical tube Nuclear Engineering and Design. 177: 53-69. DOI: 10.1016/S0029-5493(97)00185-4 |
0.345 |
|
| 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 |
0.304 |
|
| 1996 |
Peterson PF, Scott JM. The Mini-Chamber, an Advanced Protection Concept for NIF Fusion Technology. 30: 442-447. DOI: 10.13182/Fst96-A11962980 |
0.409 |
|
| 1996 |
Jin H, Peterson PF. Debris Interaction with Different Vapors and Condensed Materials in NIF Fusion Technology. 30: 436-441. DOI: 10.13182/Fst96-A11962979 |
0.329 |
|
| 1996 |
Peterson PF. Long-term safeguards for plutonium in geologic repositories Science and Global Security. 6: 1-29. DOI: 10.1080/08929889608426432 |
0.307 |
|
| 1996 |
Kuhn SZ, Peterson PF, Schrock VE. Determination of the local heat flux in condensation experiments Experimental Heat Transfer. 9: 149-163. DOI: 10.1080/08916159608946519 |
0.354 |
|
| 1996 |
Peterson PF. Theoretical basis for the Uchida correlation for condensation in reactor containments Nuclear Engineering and Design. 162: 301-306. DOI: 10.1016/0029-5493(95)01125-0 |
0.319 |
|
| 1994 |
Cavanaugh CJ, Peterson PF. Scale Modeling of Oscillating Sheet Jets for the HYLIFE-II Inertial Confinement Fusion Reactor Fusion Technology. 26: 917-921. DOI: 10.13182/Fst94-A40271 |
0.38 |
|
| 1994 |
Chen XM, Schrock VE, Peterson PF. Fitted Equations of State for Flibe Gas Fusion Technology. 26: 912-916. DOI: 10.13182/Fst94-A40270 |
0.305 |
|
| 1994 |
Chen XM, Schrock VE, Peterson PF. Coupling of Radiation Transport with the Gas Dynamics for HYLIFE-II Analysis Fusion Technology. 26: 906-911. DOI: 10.13182/Fst94-A40269 |
0.316 |
|
| 1994 |
Chen XM, Peterson PF, Tobin MT. TSUNAMI Analysis of National Ignition Facility 2-D Gas Dynamics Phenomenon Fusion Technology. 26: 814-818. DOI: 10.13182/Fst94-A40255 |
0.366 |
|
| 1994 |
Liu JC, Colella P, Peterson PF, Schrock VE. Modeling supersonic flows through a gas-continuous two-fluid medium Nuclear Engineering and Design. 146: 337-348. DOI: 10.1016/0029-5493(94)90340-9 |
0.341 |
|
| 1994 |
Peterson PF. Scaling and analysis of mixing in large stratified volumes International Journal of Heat and Mass Transfer. 37: 97-106. DOI: 10.1016/0017-9310(94)90013-2 |
0.342 |
|
| 1993 |
Peterson PF, Schrock VE, Kageyama T. Diffusion layer theory for turbulent vapor condensation with noncondensable gases Transactions - Asme: Journal of Heat Transfer. 115: 998-1003. DOI: 10.1115/1.2911397 |
0.334 |
|
| 1993 |
Schrock VE, Peterson PF, Bai RY. A gas dynamic choking phenomenon in early time intense transient condensation Nuclear Engineering and Design. 139: 127-140. DOI: 10.1016/0029-5493(93)90267-D |
0.392 |
|
| 1993 |
Kageyama T, Peterson PF, Schrock VE. Diffusion layer modeling for condensation in vertical tubes with noncondensable gases Nuclear Engineering and Design. 141: 289-302. DOI: 10.1016/0029-5493(93)90107-K |
0.362 |
|
| 1992 |
Chen XM, Schrock VE, Peterson PF. The Calculation of the Kinetic Rate Constants for LiF and BeF2 Fusion Technology. 21: 1536-1540. DOI: 10.13182/Fst92-A29938 |
0.359 |
|
| 1992 |
Chen XM, Schrock VE, Peterson PF. The Hydraulic Analysis of Cylindrical Flibe Jets in a HYLIFE-II ICF Reactor Fusion Technology. 21: 1531-1535. DOI: 10.13182/Fst92-A29937 |
0.424 |
|
| 1992 |
Chen XM, Schrock VE, Peterson PF. The Soft-Sphere Equation of State for Liquid Flibe Fusion Technology. 21: 1525-1530. DOI: 10.13182/Fst92-A29936 |
0.376 |
|
| 1992 |
Chen XM, Schrock VE, Peterson PF, Colella P. Gas Dynamics in the Central Cavity of the HYLIFE-II Reactortitle Fusion Technology. 21: 1520-1524. DOI: 10.13182/Fst92-A29935 |
0.409 |
|
| 1992 |
Liu JC, Peterson PF, Schrock VE. Blast Venting through Blanket Material in the HYLIFE ICF Reactor Fusion Technology. 21: 1514-1519. DOI: 10.13182/Fst92-A29934 |
0.41 |
|
| 1992 |
Peterson PF, Bai RY, Schrock VE, Hijikata K. Droplet condensation in rapidly decaying pressure fields Journal of Heat Transfer. 114: 194-200. DOI: 10.1115/1.2911246 |
0.349 |
|
| 1991 |
Peterson PF, Elkouh N, Lee KW, Tien CL. Flow instability and bifurcation in gas-loaded reflux thermosyphons Journal of Heat Transfer. 113: 158-165. DOI: 10.1115/1.2910520 |
0.31 |
|
| 1990 |
Peterson PF, Tien CL. Mixed double-diffusive convection in gas-loaded heat pipes Journal of Heat Transfer. 112: 78-83. DOI: 10.1115/1.2910368 |
0.351 |
|
| 1989 |
Peterson PF, Tien CL. Numerical and analytical solutions for two-dimensional gas distribution in gas-loaded heat pipes Journal of Heat Transfer. 111: 598-604. DOI: 10.1115/1.3250724 |
0.327 |
|
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