A Solvent Extraction Method for Neptunium (237) Analysis (open access)

A Solvent Extraction Method for Neptunium (237) Analysis

Technical report describing a rapid and quantitative radiochemical method for the analysis of neptunium (237). This method is based on the extraction of neptunium (IV) with thenoyl-trifluoracetone in xylene. Neptunium (237) is separated free from other alpha emitters and from non-radioactive interferences, and the method may be readily adapted to remote control. [From Abstract]
Date: July 10, 1951
Creator: Moore, Fletcher L.
System: The UNT Digital Library
Shielding Reactor Corrosion Studies (open access)

Shielding Reactor Corrosion Studies

Technical report outlining the investigation of corrosion on MTR type fuel elements for the Shielding Reactor in filtered water. Report includes two basic types of protection: element pretreatment by either anodizing or alodizing, and solution control using nitric acid to maintain a pH of 5.5 to 6.5 or the addition of 60 ppm sodium chromate as an inhibitor. [From Abstract]
Date: July 9, 1951
Creator: Olsen, Arnold R.
System: The UNT Digital Library
Physics Division Quarterly Progress Report for Period Ending March 20, 1951 (open access)

Physics Division Quarterly Progress Report for Period Ending March 20, 1951

Technical report covering classified work of the Critical Experiments Program in the Physics Division for the period December 20, 1950 to March 20, 1951. Report outlines investigations of properties of critical assemblies composed of uranium and various reflectors and moderators, preliminary measurements of the effective energy for fission in the assembly. [From Introduction and Summary]
Date: July 2, 1951
Creator: Bernstein, S.; Snell, A. H. & Wollan, E. O.
System: The UNT Digital Library