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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.

Item Type: Report

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Quarterly Technical Progress Report, AEC Unclassified Programs: July-September 1965

Quarterly report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the first quarter of the 1966 fiscal year.

Date: December 22, 1965

Creator: North American Aviation. Atomics International Division.

Item Type: Report

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Second-cycle airox reprocessing and pellet refabricating of highly irradiated uranium dioxide

"This report describes second-cycle postirradiation examination and AIROX reprocessing-refabricating of uranium dioxide irradiated to an additional 10,000 Mwd/MTU burnup."

Date: September 21, 1965

Creator: Bodine, J. E.; Guon, J. & Sullivan, R. J.

Item Type: Report

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Quarterly Progress Report, Research and Development Activities Fixation of Radioactive Residues: April-June 1965

Introduction: "This progress report is the twenty-sixth in a series presenting research and development activities in the field of radioactive wastes. Experimental work charged to programs other than those of the Division of Reactor Development is included for general interest and completeness; such work is identified in the headings."

Date: September 1965

Creator: Pacific Northwest Labortoary. Chemistry Department.

Item Type: Report

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Final Report: Investigation of Boiling Flow Regimes and Critical Heat Flux

From abstract: A program to investigate the mechanism of the critical heat flux condition from the standpoint of flow regimes has been initiated at Dynatech for the AEC. This report covers the work done on this investigation in the first year.

Date: March 1, 1965

Creator: Suo, M.; Bergles, Arthur E.; Doyle, Edward F.; Clawson, L. & Goldberg, P.

Item Type: Report

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The Development of an Improved Thermionic Energy Converter: Third Quarterly Technical Report

From introduction: The objective of the current program is to determine the feasibility of the reservoirless converter operation by conducting a series of tests on operating thermionic converters which contain cesium in the vapor phase only.

Date: April 1965

Creator: Radio Corporation of America. Direct Energy Conversion Department.

Item Type: Report

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SRE Mark II Fuel Handling Machine

Abstract: The Sodium Reactor Experiment Mark II Fuel Handling Machine has been modified to ensure fuel and gas containment during core III operation. A new fuel control system has been designed for the fuel handling machine.

Date: April 20, 1965

Creator: Dietz, H. B.

Item Type: Report

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A Rotary Kiln for the Controlled Oxidation of UC

Abstract: A rotary kiln was evaluated for the controlled oxidations of UC.

Date: June 30, 1965

Creator: Strausberg, S.

Item Type: Report

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SNAP 10A FSEM-3 Agena Compatibility Test

From abstract: This report summarizes the results of SNAP-10A/Agena developmental testing and final vehicle systems tests.

Date: June 15, 1965

Creator: Teresa, M.

Item Type: Report

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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.

Item Type: Report

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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.

Item Type: Report

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The Properties and Irradiation Behavior of U₃Si₂

Abstract: A limited study of the compound U₃Si₂ has been made in reference to its use as a prospective nuclear fuel in sodium cooled reactors.

Date: July 25, 1965

Creator: Shimizu, H.

Item Type: Report

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Development of High-Temperature Electrical Ground Test Heaters for the SNAP 10A Program

Introduction: The development and qualification of the system acceptance test heaters and the reactor simulator heater are described in this progress report.

Date: March 1, 1965

Creator: Blevitt, R.; Paine, G. & Sudar, S.

Item Type: Report

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Calculations of the Madelung Constant and Inverse Twelfth Power Repulsion Factors for the Wurtzite Crystal Structure

From abstract: The Madelung constant and the inverse twelfth power repulsion factor have been calculated for the wurtzite structure for wide ranges of the crystal parameters and u.

Date: July 25, 1965

Creator: Gehman, William G.

Item Type: Report

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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.

Item Type: Report

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Carbide Fuels in Fast Reactors

Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.

Date: September 15, 1965

Creator: Wheelock, C. W.

Item Type: Report

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Effect of Carburization on the Low Strain Rate Behavior of Type 304 Stainless Steel: Interim Report

Abstract: Pressure stress-rupture specimens of thin walled Type 304 stainless steel tubing have been tested at temperatures to 1300°F in the presence of an internal diffusion limited carbon source.

Date: August 31, 1965

Creator: Stone, D. H. & Schwartz, A. D.

Item Type: Report

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200-Mwe Prototype Large SGR: Reactor Structure Design and Evaluation

From abstract: This document presents the reactor structure design and evaluation for a 200-Mwe prototype large SGR.

Date: 1965

Creator: North American Aviation. Atomics International Division.

Item Type: Report

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Development, Acceptance and Qualification Testing of the SNAP 10A Ejectable Heat Shield

From abstract: The development, acceptance, and qualification tests performed on the SNAP-10A Ejectable Heat Shield and components, the results of those tests, and the conclusions drawn from the results are presented in this report.

Date: August 31, 1965

Creator: Sperow, H. L.

Item Type: Report

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U-10 Wt % Mo Fuel Element: Irradiation in SRE

From abstract: The fuel element assembly was successfully irradiated in the SRE to a maximum burnup of 5300 Mwd/MTU, at a peak fission rate of approximately 1.5 x 10E13 fissions/cm3-sec and a maximum central temperature near 1200F.

Date: August 31, 1965

Creator: Arnold, J. L.; Miller, K. J. & Peterson, R. M.

Item Type: Report

open access

The High-Temperature Irradiation Behavior of Hypostoichiometric Uranium Monocarbide

From abstract: A series of three multi-compartmented experiments was designed to investigate the irradiation behavior uranium carbide fuels, as a function of composition, temperature, and burn-up; and the mechanical properties of Type 304 stainless steel, as a function of temperature and integrated thermal neutron flux.

Date: August 31, 1965

Creator: Hahn, R. D.

Item Type: Report

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Large SGR Control Rod Development

From abstract: A development program was initiated to design, fabricate and test an absorber column with a 10 to 12 year lifetime, for use in the proposed LSGR.

Date: July 25, 1965

Creator: Dermer, M. D.

Item Type: Report

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Calandria Core Weld Joint Development

Abstract: The design and initial test of cutting and welding equipment developed to remotely cut and re-weld the bottom process tube joint are discussed in this report.

Date: June 30, 1965

Creator: Roberts, J. G.

Item Type: Report

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Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 5: July-December 1964

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: June 15, 1965

Item Type: Report

UNT Libraries Government Documents Department - 79 Matching Results

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Annual Technical Progress Report, AEC Unclassified Programs: 1965

Quarterly Technical Progress Report, AEC Unclassified Programs: July-September 1965

Second-cycle airox reprocessing and pellet refabricating of highly irradiated uranium dioxide

Quarterly Progress Report, Research and Development Activities Fixation of Radioactive Residues: April-June 1965

Final Report: Investigation of Boiling Flow Regimes and Critical Heat Flux

The Development of an Improved Thermionic Energy Converter: Third Quarterly Technical Report

SRE Mark II Fuel Handling Machine

A Rotary Kiln for the Controlled Oxidation of UC

SNAP 10A FSEM-3 Agena Compatibility Test

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

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

The Properties and Irradiation Behavior of U₃Si₂

Development of High-Temperature Electrical Ground Test Heaters for the SNAP 10A Program

Calculations of the Madelung Constant and Inverse Twelfth Power Repulsion Factors for the Wurtzite Crystal Structure

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

Carbide Fuels in Fast Reactors

Effect of Carburization on the Low Strain Rate Behavior of Type 304 Stainless Steel: Interim Report

200-Mwe Prototype Large SGR: Reactor Structure Design and Evaluation

Development, Acceptance and Qualification Testing of the SNAP 10A Ejectable Heat Shield

U-10 Wt % Mo Fuel Element: Irradiation in SRE

The High-Temperature Irradiation Behavior of Hypostoichiometric Uranium Monocarbide

Large SGR Control Rod Development

Calandria Core Weld Joint Development

Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 5: July-December 1964