Jeffrey J. Powers
Publications by Year
Research Areas
Nuclear reactor physics and engineering, Nuclear Materials and Properties, Nuclear and radioactivity studies, Nuclear Physics and Applications, Fusion materials and technologies
Most-Cited Works
- → Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors(2014)215 cited
- → A review of TRISO fuel performance models(2010)205 cited
- → Fully Ceramic Microencapsulated (FCM) Replacement Fuel for LWRs(2013)76 cited
- → Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE(2016)64 cited
- → Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON(2018)51 cited
- → Neutron Transport and Nuclear Burnup Analysis for the Laser Inertial Confinement Fusion-Fission Energy (LIFE) Engine(2009)48 cited
- → Advanced Demonstration and Test Reactor Options Study(2017)42 cited
- → Liquid Fuel Molten Salt Reactors for Thorium Utilization(2016)42 cited
- → Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview(2016)40 cited
- → Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems(2015)38 cited