Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report (open access)

Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report

This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees.
Date: September 12, 1958
Creator: Patton, F. S.; Bailey, J. C.; Callihan, A. D.; Googin, J. M.; Jasny, G. R.; McAlduff, H. J. et al.
System: The UNT Digital Library
Portable Mercury Vapor Detector (open access)

Portable Mercury Vapor Detector

From abstract: "This report describes a functional mercury vapor detector which is a portable, self-contained, survey instrument, and had a minimum range from zero to two-tenths milligram of mercury per cubic meter of air."
Date: March 14, 1958
Creator: McMurray, C. S. & Redmond, J. W.
System: The UNT Digital Library
Uranium Concentration Meter (open access)

Uranium Concentration Meter

From abstract; "Two basic instruments were developed for determining the concentration of uranium in solutions. Both instruments detect the gamma activity present in a sample solution, and interpret this analysis into direct presentation as parts per million."
Date: September 24, 1956
Creator: Arnett, Orville
System: The UNT Digital Library
Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant (open access)

Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant

From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
Date: September 30, 1959
Creator: Linenberger, G. A.
System: The UNT Digital Library
In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T) (open access)

In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)

Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.
Date: July 2, 1959
Creator: Nakazato, S.; Williams, P. M. & Wilson, W. D.
System: The UNT Digital Library
Floating-Decimal Matrix Inversion (open access)

Floating-Decimal Matrix Inversion

Use of Crout Method in floating-decimal notation in IBM Model I Card-Programmed Calculator.
Date: April 1955
Creator: Trantham, F. M., Jr.
System: The UNT Digital Library
Extraction of Thorium Nitrate from Nitric Acid by TBP - "Ultrasene" (open access)

Extraction of Thorium Nitrate from Nitric Acid by TBP - "Ultrasene"

Equilibrium data are presented for the distribution of thorium nitrate and nitric acid between aqueous solutions and tri-n-butyl phosphate diluted with kerosene.
Date: October 1956
Creator: Siddall, Thomas H., III
System: The UNT Digital Library
Fast Neutron Data (open access)

Fast Neutron Data

A report concerning fast neutrons including theory and compiled data.
Date: January 25, 1950
Creator: Feshbach, H.
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
Joint Design for Making Root Pass Welds without Filler Material (open access)

Joint Design for Making Root Pass Welds without Filler Material

Investigation to evaluate some of the designs, techniques, and methods for fabrication of a root pass.
Date: July 9, 1956
Creator: Lemon, L. C. & Smith, W. R.
System: The UNT Digital Library
The Purex process : a Solvent Extraction Reprocessing Method for Irradiated Uranium (open access)

The Purex process : a Solvent Extraction Reprocessing Method for Irradiated Uranium

Purex process which utilizes solvent extraction to separate and purify uranium and plutonium from each other and from fission products contained in irradiated uranium fuel elements.
Date: April 8, 1957
Creator: Irish, E. R. & Reas, W. H.
System: The UNT Digital Library
A Martensitic Reaction for Uranium (open access)

A Martensitic Reaction for Uranium

Series of isothermal transformation studies for improvement in fabrication and reactor performance of uranium fuel elements.
Date: June 25, 1957
Creator: Bement, A. L. & Wallace, W. P.
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
An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2 (open access)

An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2

Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.
Date: June 2, 1958
Creator: Spear, W. G.
System: The UNT Digital Library
Factors Affecting Fluidization of Uranium Trioxide Powders (open access)

Factors Affecting Fluidization of Uranium Trioxide Powders

Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.
Date: March 1, 1958
Creator: Johnson, B. M.
System: The UNT Digital Library
The Effect of Temperature on the Neutron Attenuation of Magnetite Concrete (open access)

The Effect of Temperature on the Neutron Attenuation of Magnetite Concrete

Comparison of experimentally determined relaxation lengths to the value calculated from the concrete composition.
Date: December 11, 1958
Creator: Wood, D. E.
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
Distribution of the Actinide Elements in the Molten System: KCI-AICI3-AI (open access)

Distribution of the Actinide Elements in the Molten System: KCI-AICI3-AI

Report of data for the distributions of elements 90 through 96 between molten salt solutions of their chlorides and molten aluminum (or alloy) at 725 Celsius.
Date: October 20, 1959
Creator: Moore, R. H. & Lyon, W. L.
System: The UNT Digital Library
An Automatic Analyzing Monitor for Reactor Effluent Cooling Water (open access)

An Automatic Analyzing Monitor for Reactor Effluent Cooling Water

From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."
Date: May 1, 1959
Creator: Rieck, H. G.; Ratcliffe, C. A. & Schwendiman, L. C.
System: The UNT Digital Library
Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes (open access)

Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes

Development of a fabrication process and the manufacture of 95 PRTR process tubes demonstrates that the commercial fabrication of high quality Zircaloy-2 pressure tubing is feasible.
Date: July 31, 1959
Creator: Knecht, R. L.
System: The UNT Digital Library
Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity (open access)

Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity

A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.
Date: June 26, 1959
Creator: Jackson, P. M.
System: The UNT Digital Library
Engineering Test Reactor : Engineering Design and Safeguards Report (open access)

Engineering Test Reactor : Engineering Design and Safeguards Report

From abstract: "Detail and engineering drawings for the Engineering Test Reactor."
Date: July 1956
Creator: Kaiser Engineers
System: The UNT Digital Library
A Neutron Absorption Alignment Chart (open access)

A Neutron Absorption Alignment Chart

From introduction: "Neutron absorption alignment chart for the measurement of neutron flux density."
Date: July 30, 1957
Creator: Nisle, Robert G.
System: The UNT Digital Library