John D Stempien

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

Characteristics of Composite Silicon Carbide Fuel Cladding after Irradiation under Simulated PWR Conditions

John D Stempien, David Carpenter, G. Kohse et al. · Nuclear Technology · 2013 · 85 citations

Engineering, Simulated Pwr Conditions, Fusion Materials +17

Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test

John Hunn, Charles A. Baldwin, Fred Montgomery et al. · Nuclear Engineering and Design · 2017 · 60 citations · Full text

Fuel Compacts, Triso Particles, Initial Examination +3

An integrated model of tritium transport and corrosion in Fluoride Salt-Cooled High-Temperature Reactors (FHRs) – Part I: Theory and benchmarking

John D Stempien, R. G. Ballinger, Charles Forsberg · Nuclear Engineering and Design · 2016 · 52 citations · Full text

Materials Science, Corrosion Technology, Chemical Engineering +7

Ceramography of irradiated TRISO fuel from the AGR-2 experiment

Francine J. Rice, John D Stempien, Paul A. Demkowicz · Nuclear Engineering and Design · 2017 · 34 citations

Natural Sciences, Spectroscopy, Irradiated Triso Fuel +2