Edward D. Blandford

Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward

Charles Forsberg, Stephen Lam, David Carpenter et al. · Nuclear Technology · 2017 · 113 citations · Full text

Engineering, Nuclear Physics, Reactor Design +21

Kairos power thermal hydraulics research and development

Edward D. Blandford, Kyle Brumback, Lambert Fick et al. · Nuclear Engineering and Design · 2020 · 82 citations · Full text

Core Thermal Hydraulics, Engineering, Thermal Hydraulics +5

Design and licensing strategies for the fluoride-salt-cooled, high-temperature reactor (FHR) technology

Raluca O. Scarlat, Michael Laufer, Edward D. Blandford et al. · Progress in Nuclear Energy · 2014 · 79 citations · Full text

Advanced Nuclear Reactors, Engineering, Reactor Design +4

Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel

Soon Lee, Maolong Liu, Nicholas R. Brown et al. · International Journal of Heat and Mass Transfer · 2018 · 55 citations · Full text

Materials Science, Critical Heat Flux, High Temperature Materials +7

Neutronics, thermal-hydraulics, and multi-physics benchmark models for a generic pebble-bed fluoride-salt-cooled high temperature reactor (FHR)

Nader Satvat, Fatih Sinan Sarikurt, Kevin Johnson et al. · Nuclear Engineering and Design · 2021 · 51 citations · Full text

Engineering, Nuclear Physics, Physics +9