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Publications by D.F. Fischer
Out-Of-Pile Study of the Effects of Thermal Gradients on the Distribution of Plutonium in Fast-Reactor Fuel Materials.
Related publications
Thermal Conductivity of Reactor Fuel Element Materials
Study of the Self-Controllability for the Fast Reactor Core With High-Thermal-Conductivity Fuel
Journal of Nuclear Science and Technology
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Use of Neutron Filters for Fast Reactor Fuel Irradiations in a Thermal Reactor Core.
Simulation of Fuel Distribution in the Inner Fast Zone for Two-Zone Subcritical Reactor
Nuclear Physics and Atomic Energy
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Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor
Science and Technology of Nuclear Installations
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Coulometric Determination of Plutonium in Solutions of Dissolved Reactor Fuel Elements.
Behavior of Actinides in the Integral Fast Reactor Fuel Cycle
Study on the Impacting Thermal Effects of PTFE/Al Energetic Materials
DEStech Transactions on Engineering and Technology Research
Fast Fuel Test Reactor-FFTR Conceptual Design Study
