The solvent-extraction performance of small scale redox IA columns using Fenske helix packing, ammonium nitrate salting agent, and unirradiated uranium (open access)

The solvent-extraction performance of small scale redox IA columns using Fenske helix packing, ammonium nitrate salting agent, and unirradiated uranium

A report which deals with the Redox IA Column studies made in small-scale columns packed with 3/16-in. Fenske helices and using NH4NO3 salting agent.
Date: April 13, 1949
Creator: Woodfield, F. W.; Bradley, J. G.; Switzer, W. O. & Merrill, E. T.
System: The UNT Digital Library
Multi-Region Simulation of Xenon Poisoning in the PRTR (open access)

Multi-Region Simulation of Xenon Poisoning in the PRTR

A previous study has been completed on the buildup and decay of xenon poisoning in the PRTR by simulating the reactor as a single region. The results of this study indicated that a study using a more refined model of the reactor would be valuable.
Date: April 13, 1959
Creator: Cameron, W. D.
System: The UNT Digital Library
Status Report on the Hanford Developed Tester for the Coextruded Fuel Elements (open access)

Status Report on the Hanford Developed Tester for the Coextruded Fuel Elements

In October 1959, a combination testing station developed at HAPO was reported to the Sheath committee. This testing station consisted of electronic instrumentation and mechanical scanning equipment to check coextruded fuel elements (rod and tube) for clad thickness, clad integrity, bond, and core integrity. The clad tests are performed by eddy current methods and the other are ultrasonic.
Date: April 13, 1960
Creator: Lambert, T. G.
System: The UNT Digital Library