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Annual Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968
Annual report with the objectives of evaluating, producing, and maintaining an up-to-date set of basic nuclear data; producing and evaluating multigroup constants; and improving of present day methods of neutronic calculations as related to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.
Date:
May 24, 1969
Creator:
unknown
System:
The UNT Digital Library
A Computer Program for Determining First-Collision Neutron Doses
Data processing program written to compute the neutron dose received by individuals exposed in a nuclear excursion.
Date:
May 21, 1962
Creator:
McMurray, C. S.
System:
The UNT Digital Library
Corrosion Studies in Simulated N-Reactor Secondary System Water Environment
Report containing the procedures and results of tests made to determine the corrosion resistance of materials in a simulation of Hanford Laboratories' N-Reactor secondary system water environment.
Date:
May 1963
Creator:
Larrick, A. P.
System:
The UNT Digital Library
Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Fourth Quarterly Progress Report, January 1-March 31, 1963
Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The experimental work centers around aspects of detecting neutrons in the presence of 10/sup 7/ r/hr gamma fields. Boric acid experiments and Humboldt Bay experiments are reported.
Date:
May 13, 1963
Creator:
Garelis, Edward & Meyer, Paul
System:
The UNT Digital Library
Dynamic Void Fraction Measurement System
Abstract: Various methods and techniques of measuring void fractions in boiling heat transfer media are discussed.
Date:
May 15, 1963
Creator:
Kendron, J. H.; Stoner, E. E. & Taylor, G. M.
System:
The UNT Digital Library
Equilibrium Dissociation Pressures of the Delta and Epsilon Phases in the Zirconium-Hydrogen System
Abstract: Pressure-temperature isochores were obtained for zirconium-hydrogen alloys, spanning the H/Zr composition range of 1.430 to 1.910. The studies were confined to the temperature limits of 300 to 900ºC, and the pressure limits of 0.01 to 10.0 atm.
Date:
May 31, 1964
Creator:
Raymond, J. W.
System:
The UNT Digital Library
The Expulsion of Liquid from a Rapidly Heated Channel
Report documenting experiments in order to determine the "behavior of a partially confined liquid in contact with a rapidly heated surface" (p. 7). These liquids include water, methanol, ethylene bromide, and acetone.
Date:
May 1967
Creator:
Singer, Ralph M.
System:
The UNT Digital Library
Feed Materials Production Center Summary Technical Report: January 1, 1963-March 31, 1963
This is a summary report of various technical projects relating to uranium.
Date:
May 10, 1963
Creator:
unknown
System:
The UNT Digital Library
Gas-Metal Reactions with Iron- and Nickel-Base Heat Resistant Alloys: An Interpretive Literature Survey
Report reviewing literature that concerns "the compatibility of stainless steels and nickel-base alloys with various gases which might be present in or around a high temperature nuclear reactor" (p. 2).
Date:
May 1963
Creator:
Jones, D. A.
System:
The UNT Digital Library
Health Physics Instrument Manual
Report issued by the Oak Ridge National Laboratory discussing a Health Physics Instrument Manual. Descriptions, characteristics, and applications of different instruments are presented. This report includes tables, illustrations, and photographs.
Date:
May 16, 1963
Creator:
Davis, D. M. & Gupton, E. D.
System:
The UNT Digital Library
The High Flux Isotope Reactor: Volume 1, A Functional Description
Report containing a description of the Oak Ridge National Laboratory's High-Flux Isotope Reactor (HFIR) and its operation.
Date:
May 1964
Creator:
Binford, F. T. & Cramer, E. N.
System:
The UNT Digital Library
Investigations of Neutron Penetration in TiH and Steel Slabs
Abstract: A multigroup P1 approximation for hydrogen scattered neutrons has been developed and applied to the study of neutron flux distributions in titanium hydride and steel shield systems.
Date:
May 15, 1961
Creator:
Karcher, R. H.
System:
The UNT Digital Library
Low-Radioactivity-Level Waste Treatment. Part II: Pilot Plant Demonstration of the Removal of Activity from Low-Level Process Wastes by a Scavenging-Precipitation Ion-Exchange Process
Report documenting the process of decontaminating low-activity fuel waste water via the Scavenging-Precipitation Ion-Exchange process. This includes analyses of the costs of the process as well as a description of the operation of the pilot plant.
Date:
May 27, 1963
Creator:
Brooksbank, R. E.; Browder, F. N.; Holcomb, R. R. & Whitson, W. R.
System:
The UNT Digital Library
Materials Testing Reactor-Engineering Test Reactor Technical Branches Quarterly Report: October 1 - December 31, 1963
From summary: "Reactor fuel material consisting of U3Si particles embedded in an aluminum matrix have been examined with an electron microprobe to determine reaction between fuel particles and matrix. Partial reaction was observed with no observable tendency for the uranium or silicon to diffuse outward into the matrix.
Date:
May 1964
Creator:
Phillips Petroleum Company
System:
The UNT Digital Library
The ML-1 Design Report
From abstract: "This report describes the design of the mobile nuclear power plant which is to be the prototype of a mobile, low-powered nuclear power plant intended to furnish electrical power in remote locations."
Date:
May 16, 1960
Creator:
Linenberger, G. A.
System:
The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Thirteenth Quarter, July-September 1962
From introduction: "This is the thirteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date:
May 15, 1963
Creator:
Pennington, R. T.
System:
The UNT Digital Library
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
OMRE Fuel Plate Surface Temperature Measurement
Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
Date:
May 1, 1960
Creator:
Sudar, S.
System:
The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: April 1967
Work is reported in these areas: general radiation effects; toxicity of radioelements; studies at the molecular and cellular levels; environmental radiation studies; atmospheric radioactivity and fallout; marine sciences; radiological and health physics; and radiation instruments.
Date:
May 1, 1967
Creator:
Fawcett, S. L.
System:
The UNT Digital Library
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
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 9: 1966
The following progress report describes the examination of elements removed in comparison to a previous study on the power facility reactor operations.
Date:
May 1969
Creator:
North American Aviation. Atomics International Division.
System:
The UNT Digital Library
Piqua Prototype Handling System
Abstract: Equipment has been developed to handle the fuel elements and control rods for the Piqua (OMR) reactor.With the handling machine, which consists of a shielded cask mounted on a gantry, a fuel element can be replaced in the core in about 27 minutes.
Date:
May 1960
Creator:
Nadler, H.
System:
The UNT Digital Library
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
A Portable Neutron Counter for Determining Weights of Deposits of Uranium-Fluorine Compounds
Abstract: A high sensitivity, portable fast neutron counter has been developed for determining the weights of solid accumulations of uranium-fluorine compounds in closed process equipment.
Date:
May 11, 1964
Creator:
Stevens, R. H. & Smith, R. C.
System:
The UNT Digital Library