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Analysis of Stresses in Bellows
Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date:
October 15, 1964
Creator:
Anderson, W. F.
System:
The UNT Digital Library
Irradiation behavior of uranium monocarbide fuel experiments NAA 81-3 and AI 3-12
A report regarding irradiation behavior of uranium monocarbide fuel experiments NAA 81-3 and AI 3-12
Date:
June 22, 1968
Creator:
Arnold, J. L.
System:
The UNT Digital Library
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
Performance of HNPF Prototype Free-Surface Sodium Pump
Abstract: A free-surface centrifugal pump, incorporating a hydraulic bearing running in sodium, was operated at the conditions required for service in the HNPF.
Date:
1960
Creator:
Atz, R. W.
System:
The UNT Digital Library
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
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 3: July-December 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:
July 15, 1964
Creator:
Auleta, J. J.
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
The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code
Abstract: FAIM is a general multigroup, one-dimensional diffusion equation code programmed in FORTRAN language for the IBM 7090 computer.
Date:
April 15, 1962
Creator:
Baller, D. C.
System:
The UNT Digital Library
Metallurgical Aspects of SRE Fuel Element Damage Episode
Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.
Date:
October 15, 1961
Creator:
Ballif, J. L.
System:
The UNT Digital Library
Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE
Abstract: A fuel material evaluation was made by destructively examining a full-scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/MTU.
Date:
June 1, 1960
Creator:
Ballif, J. L.; Hayward, B. R. & Walter, J. W.
System:
The UNT Digital Library
Evaluation of Coolant Impurity Removal Equipment at the OMRE
Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date:
October 15, 1964
Creator:
Barbour, P. & Davis, W. W.
System:
The UNT Digital Library
Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service
Abstract: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of commercially available valves considered for use in the sodium coolant system of the Hallam Nuclear Power Facility.
Date:
May 1, 1960
Creator:
Baroczy, C. J.
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
QUICKIE: A Computer Program for Spatially Independent Multigroup Slowing-Down and Thermalization Calculations
Introduction: QUICKIE is a computer program designed to solve the multigroup neutron slowing down and thermalization equations without consideration of spatial dimensions.
Date:
April 15, 1964
Creator:
Boling, M. & Rhoades, W.
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
SNAP 10A Structural Analysis
Abstract: this report discusses and summarizes all stress analysis done on the SNAP 10A system; it also mentions many of the structural tests which were accomplished.
Date:
July 15, 1964
Creator:
Boulanger, J. R.
System:
The UNT Digital Library
Critical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices
Abstract: A series of clean critical experiments was performed in the SGR critical facility utilizing 2 wt % enriched, uranium metal, hollow cylinder, fuel elements, in AGOT graphite moderator.
Date:
June 30, 1963
Creator:
Campbell, R. W.; Doyas, R. J.; Field, H. C.; Guderjahn, C. A.; Guenther, R. L.; Hausknecht, D. F. et al.
System:
The UNT Digital Library
Multi-Channel Boiling Stability for Sodium Graphite Reactors
Abstract: This report presents an analysis of coolant boiling in sodium graphite reactors.
Date:
March 1, 1962
Creator:
Cappel, H. H.
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
SNAP 2: Structural and Dynamic Analysis
Abstract: The structural design criteria and the system basic loads for the SNAP 2 compact power unit are presented.
Date:
May 1, 1964
Creator:
Castle, R. A.
System:
The UNT Digital Library
An Advanced Sodium-Graphite Reactor Nuclear Power Plant
Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date:
March 15, 1960
Creator:
Churchill, J. R. & Renard, J.
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 4: January-June 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:
December 15, 1964
Creator:
Cole, H. S.; Hausknecht, D. F.; Jenkins, O. G., Jr.; Lew, D. E.; Mandel, H.; Pearson, E. N. et al.
System:
The UNT Digital Library
Plutonium: Enriched OMR Cores
Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
Date:
May 1, 1960
Creator:
Connolly, T. J.
System:
The UNT Digital Library