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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.
System:
The UNT Digital Library
Increasing Thermocouple Reliability for in-Pile Experiments
Abstract: The results indicated that increased reliability can be obtained by using thermocouples made with insulation of increased density and/or a low thermal expansion sheath.
Date:
April 20, 1965
Creator:
Babbe, E. L.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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
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
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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
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
SRE Heat Transfer System Demolition
From introduction: This report details the extensive modifications to the SRE heat transfer systems required to accomplish increased capacity objectives.
Date:
August 31, 1965
Creator:
Nicholson, J. O.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library