Design Studies on Cesium-137 as a Source for High Level Gamma Irradiators: Quarterly Progress Report Number 3, December 1959 - March 1960 (open access)

Design Studies on Cesium-137 as a Source for High Level Gamma Irradiators: Quarterly Progress Report Number 3, December 1959 - March 1960

Quarterly progress report describing work related to a study of radiation physics problems involved in the design of high-level cesium-137 gamma sources. It outlines work completed and ongoing goals for the project.
Date: March 23, 1960
Creator: Voyvodic, Louis
System: The UNT Digital Library
SM-1 Reactor Vessel Closure Stud Investigation (open access)

SM-1 Reactor Vessel Closure Stud Investigation

Abstract: This report presents metallurgical .analyses and corrosion tests conducted to determine :causes of failure of two SM- 1 reactor vessel studs due to fracture in the threaded areas, after 23 months' operation (March 1959). Conclusions of corrosion tests are: (1) failure of the studs was caused by stress corrosion cracking, (2) contributing factors to failure of the studs were improper control of heat treatment of the studs and absence of treatment for stress relief after thread grinding operation.
Date: March 23, 1962
Creator: Reali, D. L.
System: The UNT Digital Library
A Mathematical and Statistical Approach to the Design and Analysis of a Reactor Containment Vessel Pressure Test (open access)

A Mathematical and Statistical Approach to the Design and Analysis of a Reactor Containment Vessel Pressure Test

This report discusses the mathematical and statistical questions concerned with the estimation of a leak rate from data collected during a reactor containment vessel pressure test such as that performed on the PRTR vessel in May, 1959. A mathematical method is suggested in Section 3 for the construction of a total number of gas molecules in the containment vessel time series using vessel absolute pressure and temperature readings at several positions within the vessel. A formula for the precision of the series is given in terms of the individual instrument precisions. The question of accuracy and its relationship to the temperature gradient within the vessel is also considered.
Date: March 23, 1960
Creator: Nicholson, W. L.
System: The UNT Digital Library
Volatilization of Cesium During Calcination and Hydrolysis of Cs2ZnFe(CN)6 Precipitates (open access)

Volatilization of Cesium During Calcination and Hydrolysis of Cs2ZnFe(CN)6 Precipitates

The feasibility of removing and recovering cesium-137 from various HAPO process solutions by precipitation of Cs2ZnFe(CN)6 has been demonstrated previously. Pilot plant studies of calcination and steam hydrolysis of non-radioactive Cs2ZnFe(CN)6 precipitates by members of the Process Equipment Development Operation are currently in progress. In support of these pilot plant studies, experiments were performed to determine the extent, if any, to which cesium volatilizes during calcination and hydrolysis of Cs2ZnFe(CN)6 precipitates containing cesium-137. Experimental procedures and results are presented in this report.
Date: March 23, 1960
Creator: Bouse, Donald G. & Schulz, Wallace W.
System: The UNT Digital Library