Resource Type

Annual Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968 (open access)

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
Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959 (open access)

Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959

Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
Date: May 25, 1959
Creator: Aerojet-General Corporation
System: The UNT Digital Library
A Computer Program for Determining First-Collision Neutron Doses (open access)

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 (open access)

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
Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant (open access)

Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant

Originally issued as S and P 1963A, Parts I and II. This report covers a design and feasibility study of a pebble bed reactor-steam power plant of 125 megawatt electrical output. The reactor design which evolved from this study is a two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor plus three steam generators and blowers in parallel. Plant design and system analysis including cost analysis and capital cost summary are given.
Date: May 1, 1958
Creator: unknown
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 (open access)

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
Distribution of Thermal Neutrons from Fast Sources in Exponential Piles (open access)

Distribution of Thermal Neutrons from Fast Sources in Exponential Piles

Report regarding the mathematical analysis of the exponential pile experiment using highly absorbent slugs and assuming the emitting of fast neutrons. Related theory and equations are discussed.
Date: May 27, 1954
Creator: Anselone, Philip M.
System: The UNT Digital Library
Dynamic Void Fraction Measurement System (open access)

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
Electroplated Metals on Uranium for Aluminum Cladding (open access)

Electroplated Metals on Uranium for Aluminum Cladding

Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outgassing of the nickel-plated uranium prior to aluminum cladding were beneficial, and minimizing the amount of air present in the hot-press assembly was desirable. Variation in the steps for electroplating on uranium did not affect the corrosion resistance of aluminum-clad uranium."
Date: May 4, 1955
Creator: Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
System: The UNT Digital Library
Equilibrium Dissociation Pressures of the Delta and Epsilon Phases in the Zirconium-Hydrogen System (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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
High-Level Radioactive Waste Management Alternatives Section 1: Summary, Section 2: Background and Data Base, Section 3: Evaluation Methodology (open access)

High-Level Radioactive Waste Management Alternatives Section 1: Summary, Section 2: Background and Data Base, Section 3: Evaluation Methodology

From foreword: "This report is a comprehensive overview study of potential alternative methods for long-term management of high-level radioactive waste."
Date: May 1974
Creator: Schneider, K. J. & Platt, A. M.
System: The UNT Digital Library
High-Level Radioactive Waste Management Alternatives Section 4: Geologic Disoposal (open access)

High-Level Radioactive Waste Management Alternatives Section 4: Geologic Disoposal

From foreword: "This report is a comprehensive overview study of potential alternative methods for long-term management of high-level radioactive waste...Disposal in terrestrial locations."
Date: May 1974
Creator: Schneider, K. J. & Platt, A. M.
System: The UNT Digital Library
Investigations of Neutron Penetration in TiH and Steel Slabs (open access)

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
Li⁶ and Li⁷ (n. 2n) Cross Sections at 14.1 Mev (open access)

Li⁶ and Li⁷ (n. 2n) Cross Sections at 14.1 Mev

Abstract: "An absolute measurement of the 14.1-Mev (n, 2n) cross sections of Li-6 and Li-7 has been made using the large scintillator technique, resulting in cross sections in barns of 0.070 +/- 0.006 and 0.056 +/- 0.005 for Li-6 and Li-7, respectively."
Date: May 29, 1958
Creator: Ashby, V. J.; Catron, H. C.; Newkirk, Lester L.; Taylor, C. J. & Williamson, M. A.
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 (open access)

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
Maritime Organic Moderated and Cooled Reactor (open access)

Maritime Organic Moderated and Cooled Reactor

Introduction: This document describes the results of a six-week conceptual design study of an organic moderated and cooled reactor (OMCR) power plant adapted to a Class T-7 tanker.
Date: May 27, 1959
Creator: unknown
System: The UNT Digital Library
Materials Testing Reactor-Engineering Test Reactor Technical Branches Quarterly Report: October 1 - December 31, 1963 (open access)

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
Materials Testing Reactor Project Handbook (open access)

Materials Testing Reactor Project Handbook

The following handbook was made for the purpose of: (1) to give a semidetailed description of the testing reactor, and (2) to explain, in so far as possible, the reasons for the design.
Date: May 7, 1951
Creator: Argonne National Laboratory
System: The UNT Digital Library
The ML-1 Design Report (open access)

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