Description of Purex Plant Process (open access)

Description of Purex Plant Process

Description of Purex plant process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
Date: May 19, 1959
Creator: Irish, E. R.
System: The UNT Digital Library
Fission Project Yield of Inert Gases (open access)

Fission Project Yield of Inert Gases

The final percentage of xenon created by fission in uranium and plutonium is a function of the neutron flux intensity. The flux dependence results because axenon 133 and 135 can be converted to a a stable xenon isotope by neutron capture instead of decaying into cesium.
Date: May 19, 1959
Creator: Merckx, K. R.
System: The UNT Digital Library
Quarterly Report Technology of Non-Production Reactor Fuels Processing Budget Activity 2790 (open access)

Quarterly Report Technology of Non-Production Reactor Fuels Processing Budget Activity 2790

This report summarizes the research and development work carried out during December, 1959, and January and February, 1960, for Budget Activity 2790 - Separations Development for Non-Production Reactors. The major effort on Activity 2790 has been completed. Current efforts on the remaining problem areas will enable Hanford to begin reprocessing fuel elements from power reactors which employ depleted or slightly enriched uranium fuels in July, 1962.
Date: May 19, 1960
Creator: Cooper, V. R.
System: The UNT Digital Library