Edward D. Blandford, Ph.D.
Affiliations: | 2010 | Nuclear Engineering | University of California, Berkeley, Berkeley, CA, United States |
Area:
high-temperature reactors, high level nuclear waste processing, and nuclear materials managementGoogle:
"Edward Blandford"Mean distance: 20.31
Parents
Sign in to add mentor| Per F. Peterson | grad student | 2010 | UC Berkeley | |
| (Physical Similitude in Hierarchical Engineered Systems.) | ||||
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Publications
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| Zweibaum N, Blandford E, Gerardi C, et al. (2020) Scaling Methodology for Integral Effects Tests in Support of Fluoride Salt–Cooled High-Temperature Reactor Technology Nuclear Science and Engineering. 194: 793-811 |
| Blandford E, Brumback K, Fick L, et al. (2020) Kairos power thermal hydraulics research and development Nuclear Engineering and Design. 364: 110636 |
| Lafreniere P, Zhang C, Simpson M, et al. (2020) Lab scale electrochemical codeposition experiments for comparison to computational predictions Nuclear Engineering and Technology. 52: 2025-2033 |
| Lee SK, Liu M, Brown NR, et al. (2019) Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel International Journal of Heat and Mass Transfer. 132: 643-654 |
| Ali A, Howe KJ, Blandford ED. (2018) Chemical Head Loss Measurements on Multi-Constituent Debris Beds in Small-Scale Experiments Nuclear Technology. 204: 318-329 |
| Ali AF, Gorton JP, Brown NR, et al. (2018) Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys Nuclear Engineering and Design. 338: 218-231 |
| Liu M, Hughes J, Ali A, et al. (2018) Conceptual design of a freeze-tolerant Direct Reactor Auxiliary Cooling System for Fluoride-salt-cooled High-temperature Reactors Nuclear Engineering and Design. 335: 54-70 |
| Forsberg CW, Lam S, Carpenter DM, et al. (2017) Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward Nuclear Technology. 197: 119-139 |
| Rubio F, Bond LJ, Blandford E. (2017) Scaled experiment investigating sonomechanically enhanced inert gas sparging mass transfer Nuclear Engineering and Design. 324: 171-180 |
| Liu M, Brown NR, Terrani KA, et al. (2017) Potential impact of accident tolerant fuel cladding critical heat flux characteristics on the high temperature phase of reactivity initiated accidents Annals of Nuclear Energy. 110: 48-62 |