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Raluca O. Scarlat, Ph.D. - Publications

Affiliations: 
2012 Nuclear Engineering University of California, Berkeley, Berkeley, CA, United States 
Area:
high-temperature reactors, high level nuclear waste processing, and nuclear materials management
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31 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
2022 Consiglio AN, Carotti F, Liu E, Williams H, Scarlat RO. Design and operation of a molten salt electrochemical cell. Methodsx. 9: 101626. PMID 35251944 DOI: 10.1016/j.mex.2022.101626  0.63
2020 Dbai MA, Scarlat RO, Trujillo MF. Radiative heat transfer in FLiBe molten salt participating medium in a vertical heated tube under forced and mixed convection laminar flows Nuclear Engineering and Design. 368: 110775. DOI: 10.1016/J.Nucengdes.2020.110775  0.3
2020 Wu H, Gakhar R, Chen A, Lam S, Marshall CP, Scarlat RO. Comparative analysis of microstructure and reactive sites for nuclear graphite IG-110 and graphite matrix A3 Journal of Nuclear Materials. 528: 151802. DOI: 10.1016/J.Jnucmat.2019.151802  0.362
2020 Carotti F, Liu E, Macdonald DD, Scarlat RO. An Electrochemical Study of Hydrogen in Molten 2LiF-BeF2 (FLiBe) with Addition of LiH Electrochimica Acta. 137114. DOI: 10.1016/J.Electacta.2020.137114  0.301
2020 Yao J, Qiu J, Carotti F, Scarlat R, Macdonald DD. Kinetic study of the hydrogen charging reaction on the graphite e in aqueous solution and in room temperature ionic liquid (RTIL) Electrochimica Acta. 330: 135291. DOI: 10.1016/J.Electacta.2019.135291  0.361
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  0.737
2018 Wu H, Carotti F, Gakhar R, Scarlat RO. Spectroscopy (Raman, XPS, and GDMS) and XRD analysis for studying the interaction between nuclear grade graphite and molten 2LiF-BeF (FLiBe) at 700 °C. Data in Brief. 20: 1816-1821. PMID 30294629 DOI: 10.1016/J.Dib.2018.08.079  0.302
2018 Scarlat RO. CrF2 solubility in 2LiF-BeF2: Comment on “An integrated model of tritium transport and corrosion in Fluoride Salt-Cooled High-Temperature Reactors (FHRs) – Part I: Theory and benchmarking” Nuclear Engineering and Design. 335: 389-390. DOI: 10.1016/J.Nucengdes.2018.04.021  0.312
2018 Zhang J, Forsberg CW, Simpson MF, Guo S, Lam ST, Scarlat RO, Carotti F, Chan KJ, Singh PM, Doniger W, Sridharan K, Keiser JR. Redox potential control in molten salt systems for corrosion mitigation Corrosion Science. 144: 44-53. DOI: 10.1016/J.Corsci.2018.08.035  0.343
2017 Forsberg CW, Lam S, Carpenter DM, Whyte DG, Scarlat R, Contescu C, Wei L, Stempien J, Blandford E. Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward Nuclear Technology. 197: 119-139. DOI: 10.13182/Nt16-101  0.662
2017 Forsberg CW, Carpenter DM, Whyte DG, Scarlat R, Wei L. Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors Fusion Science and Technology. 71: 584-589. DOI: 10.1080/15361055.2017.1289450  0.519
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  0.743
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.  0.477
2015 Young M, Wu H, Scarlat R. Characterization of tritium transport in the flibe-graphite system, for in-situ tritium absorption by the fuel elements of the fluoride-salt-cooled high-temperature reactor (FHR) International Topical Meeting On Nuclear Reactor Thermal Hydraulics 2015, Nureth 2015. 6: 4972-4986.  0.38
2015 Carotti F, Dbai MA, Ahmed K, Scarlat RO. Experimental and modeling studies of over-cooling transients in fluoride-salt cooled high-temperature reactors International Topical Meeting On Nuclear Reactor Thermal Hydraulics 2015, Nureth 2015. 7: 6169-6182.  0.38
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  0.655
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  0.774
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  0.725
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  0.664
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.  0.549
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.  0.735
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.  0.55
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.  0.606
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.  0.593
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.  0.603
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.  0.572
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.  0.509
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.  0.607
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  0.604
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.  0.671
2007 Kamperman M, Du P, Scarlat RO, Herz E, Werner-Zwanziger U, Graf R, Zwanziger JW, Spiess HW, Wiesner U. Composition and morphology control in ordered mesostructured high-temperature ceramics from block copolymer mesophases Macromolecular Chemistry and Physics. 208: 2096-2108. DOI: 10.1002/Macp.200700194  0.342
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