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40-tube overbore facility location, C Reactor (open access)

40-tube overbore facility location, C Reactor

Possible locations of the projected 40-tube overbore facility at the C Reactor are discussed from the standpoint of obtaining conversion ratio data applicable to a full-reactor overbore program.
Date: April 19, 1961
Creator: Nilson, R.: Nechodom, W. S.
System: The UNT Digital Library
100-KEW coolant backup adequacy (open access)

100-KEW coolant backup adequacy

None
Date: April 29, 1964
Creator: Heacock, H. W.
System: The UNT Digital Library
EEN-307, Irradiation of units at low temperature test (open access)

EEN-307, Irradiation of units at low temperature test

EWR-ESE-144, Fifty MC-890 type final assemblies were subjected to irradiation at low temperature test in order to determine if irradiation would reduce the frequency of high voltage breakdowns. A control lot of a like number of units was subjected to low temperature test in the same manner except without irradiation.
Date: April 13, 1960
Creator: Guthrie, J.B.
System: The UNT Digital Library
710 reactor-shield study support for manned spacecraft applications (open access)

710 reactor-shield study support for manned spacecraft applications

None
Date: April 1, 1967
Creator: Simpson, J.D.
System: The UNT Digital Library
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 2, Concept I System Description (open access)

1000-MWe LMFBR Follow-On Study, Task I Report: Volume 2, Concept I System Description

From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept I description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On Study Program."
Date: April 1967
Creator: Boyer, R. L.
System: The UNT Digital Library
A 1620 FORTRAN Programme for the Calculation of Bragg Angles for use in Powder X-Ray Diffraction Investigations (open access)

A 1620 FORTRAN Programme for the Calculation of Bragg Angles for use in Powder X-Ray Diffraction Investigations

An IBM 1620 program is described that calculates the Bragg angles for cubic, hexagonal, and tetragonal crystal systems for use with powder x-ray diffraction techniques. Allowance is made for absent reflections in the case of face- and body-centered cubic and close-packed hexagonal materials.
Date: April 1963
Creator: Walker, D. G.
System: The UNT Digital Library
A 1620 FORTRAN Programme for the Refinement of Lattice Parameters by a Modified Least Squares Method (open access)

A 1620 FORTRAN Programme for the Refinement of Lattice Parameters by a Modified Least Squares Method

An I.B.M. 1620 programme is described which calculates refined lattice parameters from X-ray diffraction data according to Hess' Method. The programme may be used for cubic, hexagonal, and tetragonal systems and three systematic error functions are included. The output includes the refined parameters their stand errors, and the misfit of the data at each experimental point.
Date: April 1963
Creator: Walker, D. G.
System: The UNT Digital Library
630A Maritime Nuclear Steam Generator Scoping Study (open access)

630A Maritime Nuclear Steam Generator Scoping Study

From foreword: This report presents the results of a study of a nuclear steam generator which uses reactor technology during the aircraft nuclear propulsion program to produce superheated steam for marine propulsion.
Date: April 6, 1962
Creator: General Electric Company. Flight Propulsion Division.
System: The UNT Digital Library
Absorber Burn-Up Experiment. Final Report (open access)

Absorber Burn-Up Experiment. Final Report

Experimental results are presented of pile oscillator measurements of cross sections of irradiated samples of seventeen elements. Mass spectrometer analysis of some samples was performed. Quantitative theory-experiment correlation yielded thermal absorption cross section information and also established the reliability of control rod lifetime calculations for each element investigated. Application of the results to calculation of the nuclear lifetime of reactor control rods is discussed. (auth)
Date: April 1962
Creator: Russell, J. L. Jr.; Carrothers, M. R. & Mosgovoy, W. V.
System: The UNT Digital Library
Abstracts of Available Codes at Atomics International (open access)

Abstracts of Available Codes at Atomics International

None
Date: April 1, 1964
Creator: Blaine, R. A.
System: The UNT Digital Library
ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962 (open access)

ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962

Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
Date: April 15, 1962
Creator: Combustion Engineering, inc. Nuclear Division.
System: The UNT Digital Library
ACCEL: Automated Circuit Card Etching Layout (open access)

ACCEL: Automated Circuit Card Etching Layout

None
Date: April 1, 1965
Creator: Fisk, C. J. & Isett, D. D.
System: The UNT Digital Library
Accidental nuclear excursion recuplex operation 234-5 facility: Final medical report (open access)

Accidental nuclear excursion recuplex operation 234-5 facility: Final medical report

The April 7, 1962 criticality accident involving human exposures was the first to have occurred in any production facility at Hanford. The accidental nuclear excursion did not result in any mechanical damage or spread of contamination. Three employees received over-exposure to gamma and neutron radiation. None were fatally exposed and in each case the over-exposure was recognized promptly. Following an initial period of medical observation and testing, the men were released to work. They continued to be followed clinically. Clinical studies performed were hematological procedures including leukocyte chromosome aberrations, morphologically aberrant blood cells, bone marrow evaluations, blood chemistry determinations, amino acid excretion studies, seminal fluid, urinary gonadotropins and estrogen excretion studies, testicular biopsies and crystalline lens examinations. These studies, along with a brief description of the accident and of the dosimetry, are summarized in this report by those participating in the studies. In view of the dose ranges received in these cases, both the negative and positive findings are considered to be of unusual interest due to the lack of knowledge of effects following human exposures at these levels.
Date: April 7, 1962
Creator: unknown
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962) (open access)

Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962)

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: April 1, 1962
Creator: Rider, B. F.
System: The UNT Digital Library
Activation Dose Rates From System Components (open access)

Activation Dose Rates From System Components

The report includes a summary of the results of computations to data on post-test dose rules from activated materials comprising system components and support structure.
Date: April 1, 1962
Creator: Smolen, J.R.
System: The UNT Digital Library
The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium (open access)

The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium

The adsorption of ethane, ethylene, and acetylene on clean iridium in a field emission microscope was found to cause characteristic changes in the work function of the iridium surface. Further changes, which were time and temperature dependent, resulted when such surfaces were heated. Flash filament experiments showed that the changes in work function upon henting are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a linear relationship between surface coverage and work function, it was possible to determine the desorption kinetics from the observed rates of work function change at various temperatures. The results were consistent with a mechanism involving stepwise surface dehydrogenation in which a pair of hydrogen atoms is removed from the hydrocarbon molecule in each step, followed by desorption of the adsorbed hydrogen. At very high temperatures the remainlng carbon atoms are removed, presumably by evaporation. (auth)
Date: April 1, 1962
Creator: Arthur, J. R., Jr. & Hanson, R. S.
System: The UNT Digital Library
The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium (open access)

The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium

From abstract: "The adsorption of ethane, ethylene and acetylene on clean iridium in a field emission microscope has been found to cause characteristic changes in the work function of the iridium surface. Further changes, which are time and temperature dependent, result when such surfaces are heated. Flash filament experiments have shown that the changes in work function upon heating are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a linear relationship between surface coverage and work function, it has been possible to determine the desorption kinetics from the observed rates of work function change at various temperatures. The results are consistent with a mechanism involving stepwise surface dehydrogenation in which a pair of hydrogen atoms is removed from the hydrocarbon molecule in each step, followed by desoption of the adsorbed hydrogen. At very high temperatures the remaining carbon atoms are removed, presumably by evaporation."
Date: April 7, 1962
Creator: Arthur, John R., Jr. & Hansen, Robert S.
System: The UNT Digital Library
Advanced Engineering Preliminary Program Planning, Rough Draft (open access)

Advanced Engineering Preliminary Program Planning, Rough Draft

The purpose of this document is to assembly certain job elements which may become part of the Advanced Engineerng Subsection programs, so that those individuals who may be requested to participate in such programs may be aware of the nature and form of Advanced Engineering planning.
Date: April 20, 1961
Creator: Towle, H.C.
System: The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development (open access)

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development

First part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. I-ii).
Date: April 1962
Creator: Combustion Engineering, inc. Nuclear Division.
System: The UNT Digital Library
Advanced Materials Program for January and February 1963 (open access)

Advanced Materials Program for January and February 1963

This report explains details of the Advanced Materials Program. The purpose of this program is to develop improved alloys for nuclear powerplant structural applications in the 16000F to 2000F range and for advanced applications at temperatures to 2400F or above.
Date: April 19, 1963
Creator: United States. Department of Energy.
System: The UNT Digital Library
Advanced Materials Program for January and February 1965 (open access)

Advanced Materials Program for January and February 1965

This report addresses the advanced materials program during the months of January and February of 1965
Date: April 1, 1965
Creator: United States. Department of Energy.
System: The UNT Digital Library
Aerojet-General Corporation Reliability Handbook. Volume I. Concepts (open access)

Aerojet-General Corporation Reliability Handbook. Volume I. Concepts

This report addresses the concepts of the Aeroject-General Corporation Reliaibilty Handbook
Date: April 1, 1962
Creator: unknown
System: The UNT Digital Library
AGN-GAM: an IBM 7090 Code to Calculate Spectra and Multigroup Constants (open access)

AGN-GAM: an IBM 7090 Code to Calculate Spectra and Multigroup Constants

From abstract: The IBM-7090 code is discussed together with the subroutines for writing and revising the library tapes.
Date: April 1965
Creator: Wilcox, T. P. & Perkins, S. T.
System: The UNT Digital Library
Air blast studies with animals. Part II. (open access)

Air blast studies with animals. Part II.

Goats under Nembutal and mice were exposed in a shock tube modified to give longer-duration overpressures and equipped with ports for photography. Except for ear damage, displacement still seemed to be the major cause of injury in goats in the 4-foot section of the tube. However, it was found that mice were killed, apparently by pure blast, in a particular position in a particular type of side chamber attached to the higher-pressure, smaller-diameter, section of the tube. The relation between maximum velocity of displacement and the distance animals were thrown was fairly regular. The probability of injury over different terrains is discussed. (auth)
Date: April 1, 1961
Creator: Anderson, R. S.; Stemler, F. W. & Rogers, E. B.
System: The UNT Digital Library