The Effect of X Irradiation in Oxygen and in Hydrogen at Normal and Positive Pressures on Chromosome Aberration Frequency in Tradescantia Microspores (open access)

The Effect of X Irradiation in Oxygen and in Hydrogen at Normal and Positive Pressures on Chromosome Aberration Frequency in Tradescantia Microspores

Effect of x irradiation in oxygen and in hydrogen on chromosome aberration frequency in tradescantia microspores.
Date: September 15, 1950
Creator: Giles, Norman H., Jr. & Beatty, Alvin V.
System: The UNT Digital Library
Design Analysis of a Prepackaged Nuclear Power Plant for an Ice Cap Location (open access)

Design Analysis of a Prepackaged Nuclear Power Plant for an Ice Cap Location

Report describing a the design requirements of a proposed nuclear power plant for use on an ice cap.
Date: January 15, 1959
Creator: Alco Products (Firm)
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures

Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
Date: May 15, 1962
Creator: Alco Products (Firm)
System: The UNT Digital Library
Construction Completion Report: CAI-816, 100-N Reactor Plant (open access)

Construction Completion Report: CAI-816, 100-N Reactor Plant

Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.
Date: October 15, 1964
Creator: Buckner, C. L.
System: The UNT Digital Library
Power Reactor Fuel Processing Pilot Plant: Brookhaven Fuel Program (open access)

Power Reactor Fuel Processing Pilot Plant: Brookhaven Fuel Program

Results of processing 47 metric tons of Brookhaven spent reactor fuel are summarized.
Date: December 15, 1960
Creator: McDuffee, W. T.
System: The UNT Digital Library
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak (open access)

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak

Review of previous work is presented in addition to the results of recent studies concerning loss of primary coolant when the system is cold and pressurized and the problem of supplying adequate cooling following the injection of light water.
Date: November 15, 1960
Creator: Wittenbrock, N. G. & Muraoka, J.
System: The UNT Digital Library
Ultrasonic Resin Level Detector (open access)

Ultrasonic Resin Level Detector

This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
Date: January 15, 1960
Creator: Hunter, D. O. & Pleasance, C. L.
System: The UNT Digital Library
Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1 (open access)

Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1

Specifications including detail dimension, materials, fabrication steps, acceptance criteria, and final assembly steps for the swaged uranium dioxide, 19-rod cluster Plutonium Recycle Test Reactor fuel element.
Date: March 15, 1960
Creator: Millhollen, M. K.
System: The UNT Digital Library
A Mechanism for Automatic and Manual Control of the Air Velocity at the Window Opening of Fume Hoods (open access)

A Mechanism for Automatic and Manual Control of the Air Velocity at the Window Opening of Fume Hoods

An effort to develop a control on the air velocity at the door opening of a fume hood.
Date: November 15, 1948
Creator: Weber, John, Jr.
System: The UNT Digital Library
Quarterly Progress Report Research and Development Activities Fixation of Radioactive Residues: October - December, 1964 (open access)

Quarterly Progress Report Research and Development Activities Fixation of Radioactive Residues: October - December, 1964

Report presenting research and development activities in the field of radioactive wastes. This particular report is concerned with the fixation of radioactive residues when the failure of a pot liner destroyed the furnace.
Date: April 15, 1965
Creator: Platt, A. M.
System: The UNT Digital Library
Critical Mass Studies of Plutonium Solutions (open access)

Critical Mass Studies of Plutonium Solutions

Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date: February 15, 1960
Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
System: The UNT Digital Library
Final Design Report KAPL-120 High Pressure Recirculating Water Loop (open access)

Final Design Report KAPL-120 High Pressure Recirculating Water Loop

Basic information on the design of the Knolls Atomic Power Laboratory (KAPL) -120 loop.
Date: January 15, 1956
Creator: Wade, G. E. & Berberet, J. A.
System: The UNT Digital Library
Plating Thickness Tester (open access)

Plating Thickness Tester

An electromagnetic eddy current instrument is described that is capable of measuring copper and nickel plating 1 to 8 mils thick plated on bismuth mandrils of various sizes and shapes.
Date: November 15, 1957
Creator: Fitch, C. E., Jr.
System: The UNT Digital Library
Design and Installation of a High Precision Temperature and Intimate Contact Monitor for Experimental Vacuum Chucks (open access)

Design and Installation of a High Precision Temperature and Intimate Contact Monitor for Experimental Vacuum Chucks

Describes the design criteria, design details, and final installation of a high precision temperature and intimate contact monitor.
Date: May 15, 1958
Creator: Morrow, G. W.
System: The UNT Digital Library
Trans-Plutonium Isotope Buildup by Neutron Irradiation of Plutonium (open access)

Trans-Plutonium Isotope Buildup by Neutron Irradiation of Plutonium

Graphs for estimation of plutonium and trans-plutonium isotopic content of irradiated plutonium reactor fuel of various initial isotopic compositions.
Date: December 15, 1958
Creator: Brauer, F. P. & Burley, Helen H.
System: The UNT Digital Library
Facilities for Investigation of Power Pile Materials in the High Flux Pile (open access)

Facilities for Investigation of Power Pile Materials in the High Flux Pile

Estimation of internal facilities required in the high-flux pile for research on materials for power-producing piles and components.
Date: December 15, 1955
Creator: Dietrich, J. R.
System: The UNT Digital Library
A Versatile Spectrometer Magnet Power Supply (open access)

A Versatile Spectrometer Magnet Power Supply

Early results from actual laboratory operation of a more versatile magnet supply.
Date: April 15, 1963
Creator: Groppe, W. A.
System: The UNT Digital Library
A Sequence for Predicting Waste Transport by Ground Water (open access)

A Sequence for Predicting Waste Transport by Ground Water

From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date: April 15, 1965
Creator: Nelson, R. William
System: The UNT Digital Library
Automatic Mass Spectrometer for Isotopic Analysis of Lithium (open access)

Automatic Mass Spectrometer for Isotopic Analysis of Lithium

Report discussing an improvement program on lithium mass spectrometers.
Date: March 15, 1962
Creator: McBryde, W. T. & Gammon, E. F.
System: The UNT Digital Library
Design Study: Sodium Modular Reactor (open access)

Design Study: Sodium Modular Reactor

This study was undertaken for the USAEC under Contract AT(04-3)-189, Project Agreement No. 6, to investigate desirable features of a sodium cooled, graphite moderated uranium fueled power reactor using the modular concept, and, based on this investigation, evaluate the economic potential of this reactor type.
Date: January 15, 1960
Creator: General Electric Company
System: The UNT Digital Library
Comparative Study of PuC-UC and PuO₂-UO₂ as Fast Reactor Fuel (open access)

Comparative Study of PuC-UC and PuO₂-UO₂ as Fast Reactor Fuel

From abstract: "This section, Part II, extends the comparison of two ceramic fuel systems to include the fuel cycle cost comparison in greater detail particularly with respect to fabrication and reprocessing unit costs."
Date: November 15, 1962
Creator: Collins, G. D.
System: The UNT Digital Library
Experimental Studies of Transient Effects in Fast Reactor Fuels (open access)

Experimental Studies of Transient Effects in Fast Reactor Fuels

An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO₂ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F. Multiple transient damage to the cladding is likely for transients above the melting point of the fuel.
Date: November 15, 1962
Creator: Field, J. H.
System: The UNT Digital Library
Engineering Study on Underground Construction of Nuclear Power Reactors (open access)

Engineering Study on Underground Construction of Nuclear Power Reactors

Engineering study on underground construction of nuclear power reactors.
Date: April 15, 1958
Creator: Beck, Christian
System: The UNT Digital Library
Metallurgy Research Operation: Quarterly Progress Report, January - March 1965 (open access)

Metallurgy Research Operation: Quarterly Progress Report, January - March 1965

Quarterly progress report on a project to test the radiation effects on metallurgy.
Date: April 15, 1965
Creator: Cadwell, J. J.; Bierlein, T. K.; Bement, A. L.; Dillon, R. L. & Wheeler, R. G.
System: The UNT Digital Library