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Publications by J.E. Sattizahn
Rates and Mechanisms of the Loss of Fission Products From Uranium-Graphite Fuel Materials
Related publications
Determination of Fission Products and Uranium Atoms Ejected From the Surface of Uranium-Aluminium Alloys and Uranium Metals
RADIOISOTOPES
(Fuel, Fission Product, and Graphite Technology)
The Behavior of Fission Products Captured in Graphite Powder by Nuclear Recoil. VI. The Chemical State of Iodine-131 Diffused Out From Graphite, Uranium Dioxide and Thorium Dioxide
Bulletin of the Chemical Society of Japan
Chemistry
Thermodynamics and Separation Factor of Uranium From Fission Products in “Liquid Metal-Molten Salt” System
The Adsorption of Fission Products on VHTR Structural Materials
Fission Products and Nuclear Fuel Behavior Under Severe Accident Conditions Part 3: Fission Products Speciation in the VERDON-1 Sample
Journal of Nuclear Materials
High Energy Physics
Materials Science
Engineering
Nuclear Energy
Nuclear
Non-Destructive Analysis of Uranium in Graphite Fuel Elements by Neutron Activation
Release Behavior of Metallic Fission Products From Pyrocarbon-Coated Uranium-Dioxide Particles at Extremely High Temperatures
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Utilization of Radiation From Fission Products
Nature
Multidisciplinary
