Sodium Mass Transfer: III - The Application of Liquid Ammonia as a Sodium Leaching Agent (open access)

Sodium Mass Transfer: III - The Application of Liquid Ammonia as a Sodium Leaching Agent

A technique is presented for liquid ammonia leaching of metallic sodium from corrosion coupons, filter elements, and sodium samples to reveal contaminants and impurities.
Date: April 1962
Creator: Alter, H. W. & McManus, P. A.
System: The UNT Digital Library
Final Summary Safeguards Report For The General Electric Test Reactor (open access)

Final Summary Safeguards Report For The General Electric Test Reactor

This report is submitted to the U. S. Atomic Energy Commission as a final summary safeguards and hazards evaluation of a proposed test reactor at its Vallecitos Atomic Laboratory in Alameda County of California. It is the purpose of this report to provide sufficient data to obtain an AEC facility license for the reactor.
Date: February 20, 1958
Creator: Andersen, R. K. & Jacobs, I. M.
System: The UNT Digital Library
Fabrication of Zirconium Alloys For Specific Zirconium Alloy Design Program (open access)

Fabrication of Zirconium Alloys For Specific Zirconium Alloy Design Program

The raw materials and fabrication procedures employed in preparing thirty two zirconium alloy compositions for evaluation as described in GEAP-3979 are reported. Considerations involved in the extension of reported laboratory procedures to larger scale production are discussed.
Date: December 5, 1962
Creator: Antony, K. C. & Jones, L. T.
System: The UNT Digital Library
Enclosure Pressure Calculation Method (open access)

Enclosure Pressure Calculation Method

A method of determining enclosure pressure in the event of a reactor rupture is presented and a sample calculation is shown. This method was used in calculating the design pressure of the Dresden Nuclear Power Station enclosure.
Date: October 6, 1956
Creator: Bailey, J. A.
System: The UNT Digital Library
N. S. Savannah Fuel Design and Development Program: Fuel Rod Vibration (Preliminary Report) (open access)

N. S. Savannah Fuel Design and Development Program: Fuel Rod Vibration (Preliminary Report)

This is a preliminary report on the investigation of the N.S. Savannah replacement fuel rod vibration amplitude when excited by water flowing parallel to the axis of the fuel rod. Methods of calculating the fuel rod frequency in air were verified by experiment. Work is continuing to establish the validity of methods of calculating natural frequencies in water and to confirm the correlation of flow induced vibration amplitude found in reference (1).
Date: September 25, 1959
Creator: Bailey, J. A. & Shields, C. M.
System: The UNT Digital Library
Physics Calculations for the Consumers Big Rock Point Process Computer (open access)

Physics Calculations for the Consumers Big Rock Point Process Computer

The physics calculations to be performed on the Consumers On-Line Process Computer are reported. As a result of these calculations, a three-dimensional power shape is simulated, a reactivity balance is approximated, and the neutron exposure of each third of fuel bundle and control rod are accumulated. The work was reported as a part of the Consumers Research and Development Program.
Date: May 1963
Creator: Barth, N. H.
System: The UNT Digital Library
The Development of a Scheduling Computer For The Big Rock Plant (open access)

The Development of a Scheduling Computer For The Big Rock Plant

The basic work for development of a scheduling computer for the Consumers' Big Rock Plant is outlined in this report. The computer's purpose is to make feasible higher power densities by operation closer to fuel element burnout limits, and to maximize fuel burnup.
Date: 1961
Creator: Beckjord, Eric S.
System: The UNT Digital Library
Compact Control Rod Drive Study For a Boiling Water Reactor in a T7 Tanker (open access)

Compact Control Rod Drive Study For a Boiling Water Reactor in a T7 Tanker

The reason for initiating the compact drive study for the T7 tanker was to investigate control rod drive size, location, and removal space requirement factors and select the control rod drive mechanism which would allow optimization of the over-all size of the containment vessel. Approximately twelve mechanical/hydraulic control rod drive arrangements were considered during this study.
Date: August 8, 1960
Creator: Biglieri, N. J.
System: The UNT Digital Library
Experimental Investigations of the Removal of Sodium Oxide From Liquid Sodium (open access)

Experimental Investigations of the Removal of Sodium Oxide From Liquid Sodium

Experimental investigations were conducted to obtain additional information on the growth and characteristics of sodium oxide deposits in liquid sodium which could lead to system plugging. These investigations included the removal of sodium oxide from molten sodium by the cold trap method.
Date: January 18, 1960
Creator: Billuris, G.
System: The UNT Digital Library
Compilation of Techniques Used By Vallecitos Radioactive Materials Laboratory (open access)

Compilation of Techniques Used By Vallecitos Radioactive Materials Laboratory

Equipment and techniques for remote examination of irradiated fuel assemblies applicable to the Maritime Program are described. The following subjects are covered: visual and photographic examination, dimensional measurements, gamma activity scanning, fission gas release and fuel rod void volume determinations, density measurements, metallographic examination, and radiochemical burnup analysis.
Date: February 1961
Creator: Brandt, F. A.; Mathay, P. W. & Zimmerman, D. L.
System: The UNT Digital Library
Swaging Over Unground Pellets (open access)

Swaging Over Unground Pellets

This study was designed to determine how swaging stainless steel over unground pellets will affect the integrity of fuel rods, and to find maximum pellet diameter variation that can be tolerated.
Date: January 25, 1961
Creator: Brown, R. L.
System: The UNT Digital Library
Program For the Development of Plutonium Recycle For Use in Light Water Moderated Reactors: Third Quarterly Report (open access)

Program For the Development of Plutonium Recycle For Use in Light Water Moderated Reactors: Third Quarterly Report

This is a report of work completed during the period October 1, 1961, to December 31, 1961. The Program fuel element was completed and assembled. After extensive analysis, it was concluded that the fuel was satisfactory for use in the Program.
Date: January 5, 1962
Creator: Carver, J. G.
System: The UNT Digital Library
Program For the Development of Plutonium Recycle For Use in Light Water Moderated Reactors: Quarterly Report For Period January 1 - March 31, 1962 (open access)

Program For the Development of Plutonium Recycle For Use in Light Water Moderated Reactors: Quarterly Report For Period January 1 - March 31, 1962

This is a report of work completed during the period January 1, 1962, to March 31, 1962. Work was done on fuel irradiation, activation studies and UO2 scattering experiment
Date: April 15, 1962
Creator: Carver, J. G. & Robkin, M. A.
System: The UNT Digital Library
Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Program Summary and Sixth Quarterly Report, July 1 - September 30, 1962 (open access)

Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Program Summary and Sixth Quarterly Report, July 1 - September 30, 1962

The work described in this report represents progress toward an agreement signed by the United States and the European Atomic Energy Community which provides a basis for cooperation in programs for the advancement of peaceful applications of atomic energy.
Date: October 15, 1962
Creator: Carver, J. G.; Lagache, M. P. & Morgan, W. R.
System: The UNT Digital Library
Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Quarterly Report For Period April 1 - June 30, 1962 (open access)

Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Quarterly Report For Period April 1 - June 30, 1962

The Program fuel element has continued under irradiation in the Vallecitos Boiling Water Reactor, thermal energy group transfer cross sections for UO2 have been computed, and data have been reduced from the resonance wire activations performed last quarter. Future plans are included.
Date: July 15, 1962
Creator: Carver, J. G.; Morgan, W. R. & Robkin, M. A.
System: The UNT Digital Library
Consumers Big Rock Point Nuclear Power Reactor Stability Analysis (open access)

Consumers Big Rock Point Nuclear Power Reactor Stability Analysis

This report presents the results of an analysis which was undertaken to investigate the power stability of the Consumers Big Rock Point Nuclear Power Reactor.
Date: 1964?
Creator: Case, J. M. & Holland, L. K.
System: The UNT Digital Library
Amendment No. 1 to Preliminary Hazards Summary Report For The Dresden Nuclear Power Station (open access)

Amendment No. 1 to Preliminary Hazards Summary Report For The Dresden Nuclear Power Station

Commonwealth Edison Company for the purpose of supplementing the license application for the Dresden Nuclear Power Station submits herewith Amendment No.1 to the portion of the Final Hazards Summary Report entitled Preliminary Hazards Summary Report.
Date: May 26, 1958
Creator: Commonwealth Edison Company
System: The UNT Digital Library
Amendment No. 2 To Preliminary Hazards Summary Report For The Dresden Nuclear Power Station (open access)

Amendment No. 2 To Preliminary Hazards Summary Report For The Dresden Nuclear Power Station

This report is the second amendment to the Preliminary Hazards Summary Report for the Dresden Nuclear Power Station (GEAP-1044) submitted to the United States Atomic Energy Commission on September 3, 1957.
Date: August 25, 1958
Creator: Commonwealth Edison Company
System: The UNT Digital Library
Amendment No. 4 to Hazards Summary Report For The Dresden Nuclear Power Station (open access)

Amendment No. 4 to Hazards Summary Report For The Dresden Nuclear Power Station

This report is an amendment to the Preliminary Hazards Summary Report (1) and the Operating Procedures and Emergency Plans (5) for the Dresden Nuclear Power Station, submitted to the United States Atomic Energy Commission on September 3, 1957, and June 5, 1958, respectively.
Date: February 6, 1959
Creator: Commonwealth Edison Company
System: The UNT Digital Library
Enclosure Section of the Hazards Summary Report for the Dresden Nuclear Power Station (open access)

Enclosure Section of the Hazards Summary Report for the Dresden Nuclear Power Station

The General Electric Company is designing and building a 180,000 kilowatt nuclear power plant for the Commonwealth Edison Company at a site near the confluence of the Kankakee and Des Plaines Rivers in Grundy County, Illinois, about 47 miles southwest of Chicago. The plant will be known as the Dresden Nuclear Power Station, and will employ a nuclear reactor of the dual-cycle boiling water type.
Date: January 24, 1957
Creator: Commonwealth Edison Company
System: The UNT Digital Library
Operating Procedures and Emergency Plans for the Dresden Nuclear Power Station (open access)

Operating Procedures and Emergency Plans for the Dresden Nuclear Power Station

The General Electric Company is designing and building a 180,000 kilowatt nuclear power plant for the Commonwealth Edison Company at a site 47 miles southwest of Chicago. The construction permit was issued on May 4, 1956 but is subject to submittal to the Commission of a final hazards summary report and a finding by the Commission that the final design provides reasonable assurances that the health and safety of the public will not be endangered by operation of the reactor in accordance with the specified procedures.
Date: June 5, 1958
Creator: Commonwealth Edison Company
System: The UNT Digital Library
Plan For VBWR Stability Experiment (open access)

Plan For VBWR Stability Experiment

Stability tests are to be made in the VBWR (boiling water reactor). The tests are of three types: steady state measurements, rod oscillator tests, and transient tests.
Date: August 30, 1961
Creator: Cook, W. H.; Hodde, J. A.; Howard, C. L. & Niemi, R. O.
System: The UNT Digital Library
Shielding on a 27,300 SHP Boiling Water Reactor Marine Propulsion System (open access)

Shielding on a 27,300 SHP Boiling Water Reactor Marine Propulsion System

This report summarizes the radiation and shielding analysis for a 30,000 SHP natural circulation boiling water reactor for ship propulsion. The reactor is proposed for installation in a 60,000 DWT, 18 knot tanker of the T-7 class.
Date: July 25, 1959
Creator: Craig, W. D.
System: The UNT Digital Library
Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report: April 1, 1961-June 30, 1961 (open access)

Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report: April 1, 1961-June 30, 1961

This report covers the S-I-5-B-M* fuel irradiation in the GETR Maritime Loop during the fourth quarter of fiscal year 1961. The data are summarized in Section II.
Date: August 25, 1961
Creator: Danielson, D. W.
System: The UNT Digital Library