journal article·1993-06

Development of trail, a simulation code for the molten salt electrorefining of spent nuclear fuel

Tsuguyuki Kobayashi, Moriyasu Tokiwai

Journal of Alloys and Compounds· Volume 197· Issue 1
Publisher page

Abstract

No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.

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Research context

OpenAlex topics: Molten salt chemistry and electrochemical processes · Nuclear reactor physics and engineering · Nuclear Materials and Properties

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (13)

Show source-provided references
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2. Pyrometallurgical processing of Integral Fast Reactor metal fuels
3. Chemical basis for pyrochemical reprocessing of nuclear fuel10.1021/ie00049a022 ↗
4. Molten salt electrorefining of metallic fuel. I. Electrotransportation of uranium
5. Molten salt electrorefining of metallic fuel. II. Electrorefining of U and Nd
6. Voltametry of uranium and plutonium in molten LiCl-NaCl-CaCl2-BaCl2. I. Reduction of U(III) to uranium metal10.1149/1.2095904 ↗
7. Hesson · J. Electrochem. Technol. · 1965 · 3 · 240
8. Pu-Cd system: thermodynamics and partial phase diagram
9. Thermodynamics of the uranium-cadmium system
10. Thermodynamics of cadmium- and zinc-rich alloys in the Cd-La, Cd-Ce, Cd-Pr, Zn-Ce and Zn-Pr systems10.1007/BF02811772 ↗
11. Ackerman · 1991
12. Uranium transport to solid electrodes in pyrochemical reprocessing of nuclear fuel10.1149/1.2069109 ↗
13. Tomczuk · 1991