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Publications by T.B. Lindemer
Simulated Fission Product Oxide Behavior in Triso-Coated HTGR Fuel
Thermodynamic Factors Affecting UC1-xNxIrradiation and Synthesis
Related publications
Wet-Chemical Dissolution of TRISO-coated Simulated High-Temperature-Reactor Fuel Particles
Journal of Nuclear Materials
High Energy Physics
Materials Science
Engineering
Nuclear Energy
Nuclear
Fission Product Control in HTGR Plants
Measurement and Modelling of Postirradiation Fission Product Release From HTGR Fuel Particles Under Accident Conditions
Modeling of the Repository Behavior of TRISO Fuel.
Experimental Test of the Frevap-8 Code for Calculating Metal Fission Product Release From HTGR Fuel Elements.
(Fuel, Fission Product, and Graphite Technology)
Fission Product Inventory and Decay Heat Associated With FTR Fuel.
Some Fire and Fission Product Release Possibilities for Discharged Fuel Slugs
Behavior of Fission Gases in Nuclear Fuel: XAS Characterization of Kr in UO2
Journal of Nuclear Materials
High Energy Physics
Materials Science
Engineering
Nuclear Energy
Nuclear
