Annual Technical Progress Report, AEC Unclassified Programs: 1965 (open access)

Annual Technical Progress Report, AEC Unclassified Programs: 1965

Annual report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the 1964-65 fiscal year.
Date: November 10, 1965
Creator: North American Aviation. Atomics International Division.
System: The UNT Digital Library
Environmental Monitoring Semiannual Report: January-June 1962 (open access)

Environmental Monitoring Semiannual Report: January-June 1962

From summary: This report summarizes environmental monitoring results for the first six months of 1962.
Date: November 1962
Creator: Moore, J. D.; Fisher, W. L. & Rowe, P. A.
System: The UNT Digital Library
Graphical Aids in the Calculation of the Shielding Requirements for Spent U²³⁵ Fuel (open access)

Graphical Aids in the Calculation of the Shielding Requirements for Spent U²³⁵ Fuel

Abstract: The data presented herein, in the form of graphs, can be used to obtain the value of this energy.
Date: November 15, 1957
Creator: Ashley, R. L.
System: The UNT Digital Library
Hot-Pressure Bonding of OMR Fuel Plates (open access)

Hot-Pressure Bonding of OMR Fuel Plates

Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date: November 15, 1959
Creator: Alm, G. V.; Binstock, M. H. & Garrett, E. E.
System: The UNT Digital Library
Organic Moderated Reactor Experiment Progress Report: August-October 1956 (open access)

Organic Moderated Reactor Experiment Progress Report: August-October 1956

Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the second report of the series, and covers the period from August 1, 1956 through October 31, 1956" (p. 3).
Date: November 15, 1957
Creator: Trilling, C. A.
System: The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963 (open access)

Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963

Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: November 30, 1963
Creator: Auleta, J. J.
System: The UNT Digital Library
A Remotely Controlled Welding Device for Joining Stainless Steel Tubes (open access)

A Remotely Controlled Welding Device for Joining Stainless Steel Tubes

Abstract: The design and testing of experimental equipment for remotely joining stainless steel tubing by heliarc welding is described. This apparatus consists of a modified heliarc welding torch which is hydraulically controlled to maintain constant arc voltage. A suitable arc voltage sensing and control amplifier circuit was developed for this application.
Date: November 15, 1954
Creator: Mueller, Martin & Hecker, Eugene
System: The UNT Digital Library
SRE Fuel Element Damage: An Interim Report (open access)

SRE Fuel Element Damage: An Interim Report

Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Date: November 30, 1959
Creator: Jarrett, A. A.
System: The UNT Digital Library
Terminal Status Report for the Processing Refabrication Experiment (open access)

Terminal Status Report for the Processing Refabrication Experiment

Introduction: A low-capacity, low-decontamination plant can be built, as part of a power reactor complex, to avoid long distance transfer of fuel to a high-capacity aqueous processing plant. Activation of such a complex, with the processing plant adjacent to the reactor it serves, could decrease the cost of the integrated fuel cycle. The study of this concept is a major objective of the Processing Refabrication Experiment (PRE).
Date: November 15, 1959
Creator: Sinizer, D. I.; Mattern, K. L. & Kendall, E. G.
System: The UNT Digital Library