Amanote Research

Amanote Research

    RegisterSign In

Decontamination of the Ornl Molten-Salt Flouride-Volatility Pilot Plant After Processing Irradiated Zirconium-Uranium Alloy Fuel

doi 10.2172/4582197
Full Text
Open PDF
Abstract

Available in full text

Date

February 1, 1966

Authors
S. MannE.L. Youngblood
Publisher

Office of Scientific and Technical Information (OSTI)


Related search

Molten-Salt Breeder Reactor Fuel Processing.

1972English

Bibliography of Rover Fuel Processing and Molten Salt Fluoride Volatility Process Development Studies at Oak Ridge National Laboratory

1964English

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

The International Journal of Applied Radiation and Isotopes
1985English

Experience With Processing Irradiated Fuel at the Savannah River Plant (1954--1976)

1977English

Some Studies on the Uranium - Thorium - Zirconium Ternary Alloy System

English

Thermodynamics in the Fused Salt Dissolution Process for Zirconium Fuel

1959English

Engineering Evaluation of Volatility Pilot Plant Equipment

1960English

Polarization Effects in the Molten Salt Electrorefining of Spent Nuclear Fuel

Journal of Nuclear Science and Technology
High Energy PhysicsNuclearEngineeringNuclear Energy
1995English

Production Cycle for Large Scale Fission Mo-99 Separation by the Processing of Irradiated LEU Uranium Silicide Fuel Element Targets

Science and Technology of Nuclear Installations
EngineeringNuclear Energy
2013English

Amanote Research

Note-taking for researchers

Follow Amanote

© 2025 Amaplex Software S.P.R.L. All rights reserved.

Privacy PolicyRefund Policy