Michael R. Laufer, Ph.D.
Affiliations: | 2013 | Nuclear Engineering | University of California, Berkeley, Berkeley, CA, United States |
Area:
high-temperature reactors, high level nuclear waste processing, and nuclear materials managementGoogle:
"Michael Laufer"Mean distance: 20.31
Parents
Sign in to add mentorPer F. Peterson | grad student | 2013 | UC Berkeley | |
(Granular Dynamics in Pebble Bed Reactor Cores.) |
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Publications
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Andreades C, Cisneros AT, Choi JK, et al. (2016) Design summary of the Mark-I pebble-bed, fluoride salt-cooled, high-temperature reactor commercial power plant Nuclear Technology. 195: 223-238 |
Buster GC, Laufer MR, Peterson PF. (2016) 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 |
Scarlat RO, Laufer MR, Blandford ED, et al. (2014) Design and licensing strategies for the fluoride-salt-cooled, high-temperature reactor (FHR) technology Progress in Nuclear Energy |
Zweibaum N, Cao G, Cisneros AT, et al. (2014) Phenomenology, methods and experimental program for fluoride-salt-cooled, high-temperature reactors (FHRs) Progress in Nuclear Energy. 77: 390-405 |
Krumwiede DL, Andreades C, Choi JK, et al. (2014) 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 |
Peterson F, Laufer MR, Blandford ED. (2014) Nuclear freeze Foreign Affairs. 93 |
Blandford ED, Laufer MR, Peterson PF. (2012) Development of risk metrics for the fluoride salt-cooled high temperature reactor Transactions of the American Nuclear Society. 107: 911-914 |
Cisneros AT, Scarlat RO, Laufer MR, et al. (2012) Pebble fuel design for the PB-FHR International Congress On Advances in Nuclear Power Plants 2012, Icapp 2012. 2: 900-910 |
Bickel JE, Laufer MR, Li L, et al. (2010) 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 |