The oxide chemistry of plutonium in molten fluorides and the free energy of formation of PuF3 and PuF4

Author:

Bamberger C.E.,Ross R.G.,Baes C.F.

Publisher

Elsevier BV

Subject

Materials Chemistry,Polymers and Plastics

Reference17 articles.

1. Number 2 issue of Nucl. Appl. Tech. 8 (1970); entirely devoted to Molten Salt Reactor Technology.

2. Chemical Feasibility of Fueling Molten Salt Reactors with PuF3;Thoma;ORNL-TM-2256,1968

3. SOLUBILITY OF PLUTONIUM TRIFLUORIDE IN FUSED-ALKALI FLUORIDE—BERYLLIUM FLUORIDE MIXTURES1

4. Solubility of cerium trifluoride in molten mixtures of lithium, beryllium, and thorium fluorides

5. Symposium on the Reprocessing of Nuclear Fuels;Baes,1969

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1. X‐ray diffraction, differential scanning calorimetry and evolved gas analysis of aged plutonium tetrafluoride (PuF4);Journal of Radioanalytical and Nuclear Chemistry;2021-06-23

2. Molten Salt Reactor Fuel and Coolant;Comprehensive Nuclear Materials;2020

3. Material Performance in Molten Salt;Comprehensive Nuclear Materials;2020

4. Molten Salt Reactor Fuel and Coolant;Comprehensive Nuclear Materials;2012

5. Recent Research Trends of Thorium Fuel Cycle;Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan;2006

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