Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office (open access)

Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office

Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
System: The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: April 1969 (open access)

Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: April 1969

Progress is updated for projects related mostly to biological and ecological radiation effects.
Date: May 1, 1969
Creator: Albaugh, F. W.
System: The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: June 1969 (open access)

Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: June 1969

Progress is updated for projects related mostly to biological and ecological radiation effects.
Date: July 1, 1969
Creator: Albaugh, F. W.
System: The UNT Digital Library
Halogen Collector Test Program (open access)

Halogen Collector Test Program

Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date: March 1, 1960
Creator: Arthur D. Little, Inc.
System: The UNT Digital Library
Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE (open access)

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
Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service (open access)

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
The Elimination of Microwave Reflections (open access)

The Elimination of Microwave Reflections

Abstract: "The reflections of microwaves from the walls of a plasma-containing vessel are studied. The probable cause of the reflections is discussed, and several suggestions are made for eliminating the reflections from the waveguide in the vessel and particularly from the pyrex vessel wall and copper tubing surrounding the pyrex. Quarter-wave-thick carbon-filled plastics or glasses having a very low vapor pressure room most promising when placed inside the pyrex cylinder. BaTiO3 appears to be an excellent material when placed outside the vacuum."
Date: February 1, 1955
Creator: Beard, David
System: The UNT Digital Library
Development of High-Temperature Electrical Ground Test Heaters for the SNAP 10A Program (open access)

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
Nuclear Reactor Project Progress Report, January 1948 (open access)

Nuclear Reactor Project Progress Report, January 1948

This report is a progress report detailing operations and ongoing projects at the Brookhaven National Laboratory. The report describes new developments with buildings and progress regarding ongoing experiments. The report includes photographs showing progress in the construction of the reactor and other images and figures that accompany the descriptions of projects.
Date: January 1, 1948
Creator: Borst, L. B. & Fox, Marvin
System: The UNT Digital Library
Measurement of the Behavior of a Plasma in a Magnetic Field by Means of Probes (open access)

Measurement of the Behavior of a Plasma in a Magnetic Field by Means of Probes

Abstract: "Probes were used to measure certain properties of the cloud of positive ions and electrons ejected from a pulsed ion source having two hydrogen-loaded electrodes. Time-of-flight measurements show: the presence of H+ ions with 50 ev directed energy; an increase of this energy with increasing pulse current in the source; a higher peak yield of ions with higher peak currents in the source; and higher yields and higher ion energies up to 110 ev have been recorded with the use of a pulsed magnetic field impressed upon the source. The neutral positive ion-electron beam from the source has been projected against an increasing magnetic field and the reflected and transmitted signals have been recorded and compared as a function of the magnetic field. Probe signals from the plasma as it encounters the magnetic field are oscillatory, suggesting that magnetohydrodynamic phenomena are presented."
Date: December 1, 1954
Creator: Bostick, W. H.; Zizzo, S. G. & Cook, Buford
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
Salt Bath Heat Transfer Rates for Uranium Plate (open access)

Salt Bath Heat Transfer Rates for Uranium Plate

Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
Date: February 1, 1962
Creator: Burditt, R. B.
System: The UNT Digital Library
Multi-Channel Boiling Stability for Sodium Graphite Reactors (open access)

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 (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
SNAP 2: Structural and Dynamic Analysis (open access)

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
MTR Technical Branch Quarterly Report, Third Quarter (open access)

MTR Technical Branch Quarterly Report, Third Quarter

Quarterly report for the technical branch of the Materials Testing Reactor of Idaho. Includes current developments and experiments.
Date: November 1, 1956
Creator: Conner, W. P.
System: The UNT Digital Library
Plutonium: Enriched OMR Cores (open access)

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
Operational Characteristics of Submerged Gas-Lift Circulators (open access)

Operational Characteristics of Submerged Gas-Lift Circulators

Report that presents and interprets data taken from previous tests involving gas-lift circulators and then correlates the data for the purpose of design and operational improvements.
Date: December 1, 1955
Creator: Cook, M. W. & Waters, Elmer Dale, 1930-
System: The UNT Digital Library
OMR Degasifier Loop Experiment (open access)

OMR Degasifier Loop Experiment

Abstract: A loop has been constructed to study the removal of water and highly volatile materials from Organic Moderated Reactor coolant by vacuum degasification. An analysis of the process was made to determine the most important parameters for study during the experimental program.
Date: May 1, 1960
Creator: Corporales, G. W. & Benson, P. R.
System: The UNT Digital Library
Routine Testing and Calibration Procedures for Multichannel Pulse Analyzers and Gamma-Ray Spectrometers (open access)

Routine Testing and Calibration Procedures for Multichannel Pulse Analyzers and Gamma-Ray Spectrometers

Report describing the results of laboratory tests with procedures for calibration of equipment and performance requirements.
Date: November 1, 1963
Creator: Crouch, D. F. & Heath, R. L.
System: The UNT Digital Library
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 2, March-August 1963 (open access)

Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 2, March-August 1963

From summary: The full 140 element loading of the core was completed on October 10, 1962. At this point, critical operation was begun for operator training and post-critical testing purposes.
Date: March 1, 1964
Creator: Darley, D. K.
System: The UNT Digital Library
UC Fuel Element Design and Fabrication (open access)

UC Fuel Element Design and Fabrication

Abstract: Uranium monocarbide shows considerable potential for use as a fuel in high temperature, high power density, nuclear power reactors. As Atomics International is proposing its use in sodium graphite type reactors, it was necessary to develop a process for fabricaing sodium bonded uranium carbide fuel elements.
Date: August 1, 1964
Creator: Draganchuk, W.
System: The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: February 1967 (open access)

Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: February 1967

Areas of work reported include: general radiation effects; toxicity of radioelements; combating detrimental effects of radiation; studies at the molecular and cellular level; environmental radiation studies; atmospheric radioactivity and fallout; marine sciences; radiological and health physics; and radiation instruments.
Date: March 1, 1967
Creator: Fawcett, S. L.
System: The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: March 1967 (open access)

Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: March 1967

Areas of work reported include: general radiation effects; toxicity of radioelements; studies on the molecular and cellular levels; environmental radiation studies; atmospheric radioactivity and fallout; marine sciences; radiological and health physics; and radiation instruments.
Date: April 1, 1967
Creator: Fawcett, S. L.
System: The UNT Digital Library