N-Reactor Operational Safety Review (open access)

N-Reactor Operational Safety Review

Report describing a series of tests performed to review the safety procedures and systems of Hanford Laboratories' N-Reactor.
Date: August 19, 1963
Creator: Trumble, R. E.
System: The UNT Digital Library
EOCR Control Rod and Driver Fuel Hydraulic Tests (open access)

EOCR Control Rod and Driver Fuel Hydraulic Tests

Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.
Date: October 19, 1962
Creator: Harrison, L. J.
System: The UNT Digital Library
Hazards Report for the SM-1 Core II Without Special Components (open access)

Hazards Report for the SM-1 Core II Without Special Components

Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II without special components. The SM-1 Core II components were made to specifications very nearly identical to those of SM-1 Core I. The differences consist of europium absorber sections, internal europium flux suppressors in the control rod fuel elements, and low impurity cladding. Each of the SM-1 Core II components with the exception of the five absorber sections new in SM-1 Core I were subjected to a Zero Power Experiment at the Alco Critical Facility. The results of this experiment indicate that the SM-1 Core II will have nuclear characteristics very similar to that of the SM-1 Core I. Since SM-1 Core II will be operated with the same mode of rod control, in the same core support structure, and with the same primary coolant flow conditions, the thermal characteristics should be essentially identical to that of SM-1 Core I. Also, all kinetic characteristics of SM-1 Core II should be identical to those of SM-1 Core I. This report demonstrates that there is no increase in potential for a hazardous situation at SM-1 due to the replacement of SM-1 Core I by …
Date: April 19, 1961
Creator: Gallagher, J. G.
System: The UNT Digital Library
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