Gas-Cooled Reactor Project Semiannual Progress Report: September 1964 (open access)

Gas-Cooled Reactor Project Semiannual Progress Report: September 1964

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 1965
Creator: Trauger, D. B. & Whitman, G. D.
System: The UNT Digital Library
Microscopic and Autoradiographic Studies of Distribution of Uranium in the Rat Kidney (open access)

Microscopic and Autoradiographic Studies of Distribution of Uranium in the Rat Kidney

Report issued by the Oak Ridge National Laboratory discussing studies conducted on uranium retention in rat kidneys. Methods, equipment, and results of the studies are presented. This report includes tables, illustrations, and photographs.
Date: February 1965
Creator: Jones, Edith Seymour
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1964 (open access)

Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1964

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date: February 15, 1965
Creator: Aerojet-General Corporation
System: The UNT Digital Library
Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel (open access)

Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel

The experiments described in this report were performed for two purposes: (1) to find a chemical, or combination of chemicals, that would be effective for inhibiting corrosion of steel in static portions of the Hanford water systems, and (2) as screening tests to select candidate mixtures for further testing to replace sodium dichromate as the inhibitor of aluminum and steel corrosion in the Hanford single-pass reactor cooling water.
Date: February 1965
Creator: Richman, R. B.
System: The UNT Digital Library
Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core (open access)

Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core

From abstract: "explain all important features pertaining to a new pulsed irradiation reactor, the Capsule Driver, Core, and to analyze the potential problems and hazards of operating this reactor in the existing Spert IV facility."
Date: February 1965
Creator: Miller, R. W.; McCardell, Richard K. & Lagier, T. F.
System: The UNT Digital Library
Experience in the Shipment of Yankee Fuel Assemblies for Post-Irradiation Examination (open access)

Experience in the Shipment of Yankee Fuel Assemblies for Post-Irradiation Examination

From abstract: This report presents the knowledge and experience gained from fifteen spent Yankee Core I fuel assemblies shipments. It discusses the equipment employed, the approvals required, and the technical and administrative problems that had to be resolved.
Date: February 1965
Creator: James, B.; Payne, D. D. & Walchli, H. E.
System: The UNT Digital Library
Irradiation Swelling, Phase Reversion, and Intergranular Cracking of U-10 wt % Mo Fuel Alloy (open access)

Irradiation Swelling, Phase Reversion, and Intergranular Cracking of U-10 wt % Mo Fuel Alloy

Abstract: A fuel development program has been conducted, to investigate the behavior of U-10 wt% Mo alloy at the fission rates and temperatures anticipated in Core I of the Hallam Nuclear Power Facility.
Date: February 1, 1965
Creator: Willard, R. M. & Schmitt, A. R.
System: The UNT Digital Library
The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1 (open access)

The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1

Abstract: Atomics International conducted a fuel irradiation program to investigate and define the behavior of U-10 Mo fuel at the temperatures and fission rates anticipated in Hallam Nuclear Power Facility (HNPF) Core I.
Date: February 1, 1965
Creator: Schmitt, A. R.; Willard, R. M. & Magnus, D. K.
System: The UNT Digital Library
Final Design of Sodium-Heated, Modular, Steam Generators for the SCTI (open access)

Final Design of Sodium-Heated, Modular, Steam Generators for the SCTI

Abstract: The following report covers the final design of the modular steam generators.
Date: February 1, 1965
Creator: Casey, D. F.; Hammer, J. J.; Logan, D. & Williams, M. C.
System: The UNT Digital Library
Flux Control for Irradiation Experiments (open access)

Flux Control for Irradiation Experiments

Abstract: This report reviews various means which have been used to control experimental conditions in irradiation experiments, and presents the concept of local flux control.
Date: February 1, 1965
Creator: McCarty, W. K.
System: The UNT Digital Library
Comparative Fuel Cycle Evaluations, Low Decontamination Pyroprocessing, and Aqueous Reprocessing: Part 2. UC Fuel in a Thermal Reactor (open access)

Comparative Fuel Cycle Evaluations, Low Decontamination Pyroprocessing, and Aqueous Reprocessing: Part 2. UC Fuel in a Thermal Reactor

From abstract: Preliminary cost estimates for fuel cycles using both aqueous and CARBOX reprocessing are presented.
Date: February 15, 1965
Creator: Mattern, K. L. & Colby, L. J., Jr.
System: The UNT Digital Library
Application of Nuclear Power Plants (SNAP Units) to the Manned Orbiting Research Laboratory (MORL) (open access)

Application of Nuclear Power Plants (SNAP Units) to the Manned Orbiting Research Laboratory (MORL)

Abstract: This report describes in detail two designs of a nominal 6-kwe Nuclear Power Plant (NPP), one using thermoelectrics for power conversion and the other using the Mercury-Rankine cycle NPP.
Date: February 1, 1965
Creator: Botts, W. V.; Marko, M.; McCourt, P. E.; Keshishian, V.; Piccot, A. R. & Budney, G. S.
System: The UNT Digital Library
Fatigue Characteristics of 37-Tube, Modular, Steam Generator Head (open access)

Fatigue Characteristics of 37-Tube, Modular, Steam Generator Head

Abstract: This report presents the pertinent results of a series of fatigue tests relating to the evaporator and superheater 37-tube module heads for the sodium heated steam generator described in NAA-SR-9826.
Date: February 20, 1965
Creator: Lemcoe, M. M.
System: The UNT Digital Library
Evaluated Neutron Cross Sections for Tritium (open access)

Evaluated Neutron Cross Sections for Tritium

From foreword: Evaluation of the experimental data on the light isotopes, hydrogen through beryllium, was initiated by LASL in mid-1963. Since the data compilations available were completely inadequate for the task at hand, the tedious program of compiling and plotting was undertaken. As the work progressed an attempt was made to eliminate many of the obvious errors and inconsistencies found in the literature and existing compilations.
Date: February 1965
Creator: Stewart, Leona
System: The UNT Digital Library