Thermodynamics and Separation Factor of Uranium From Fission Products in “Liquid Metal-Molten Salt” System

doi 10.5772/intechopen.72451
Full Text
Abstract

Available in full text

Date
Authors
Publisher

InTech

Related search

Extractor Type in Liquid Metal-Molten Salt Extraction System.

Journal of Nuclear Science and Technology
High Energy PhysicsNuclearEngineeringNuclear Energy
1988English

Reprocessing of Uranium Fuels by Selective Oxidation-Reduction Reactions in a Fused Salt-Liquid Metal System

English

Reprocessing of Uranium Fuels by Selective Oxidation-Reduction Reactions in a Fused Salt-Liquid Metal System

English

Determination of Fission Products and Uranium Atoms Ejected From the Surface of Uranium-Aluminium Alloys and Uranium Metals

RADIOISOTOPES
1972English

Cost of Processing Fuel From a Molten Salt, Fusion-Fission, Hybrid Reactor Blanket

The International Journal of Applied Radiation and Isotopes
1985English

The Thermodynamics of the Reduction of Uranium Compounds to Uranium Metal

1952English

Rates and Mechanisms of the Loss of Fission Products From Uranium-Graphite Fuel Materials

1961English

Molten-Salt Synthesis of Complex Metal Oxide Nanoparticles

Journal of Visualized Experiments
ImmunologyMolecular BiologyBiochemistryMicrobiology Chemical EngineeringNeuroscienceGenetics
2018English

Dissolution of Uranium Metal Into Molten MgCl2-LiCl-KCl

Denki Kagaku oyobi Kogyo Butsuri Kagaku
1975English

Amanote Research

Note-taking for researchers

Follow Amanote

© 2024 Amaplex Software S.P.R.L. All rights reserved.

Privacy PolicyRefund Policy