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Spectral Representation and Criticality Problem of a Two-Region Cell Transport Operator (open access)

Spectral Representation and Criticality Problem of a Two-Region Cell Transport Operator

Report determining the solution of the transport equation to determine accurate conditions for the criticality of a two-region fuel-moderator assembly with reflecting boundaries.
Date: 1965
Creator: Pollack, Israel & Bareiss, Erwin
System: The UNT Digital Library
Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies (open access)

Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies

Report describing a pilot plant constructed at Argonne National Laboratory for studying two major process steps for the recovery of uranium and plutonium from spent nuclear fuels of power reactors. A major objective is the demonstration of optimum process conditions for the two steps for synthetic reactor fuel compositions, including those containing mixtures of inactive fission products.
Date: 1964
Creator: Vogel, G. J.; Carls, E. L. & Mecham, W. J.
System: The UNT Digital Library
Metallurgy Division Quarterly Report [for] October, November, and December 1955 (open access)

Metallurgy Division Quarterly Report [for] October, November, and December 1955

A total of nine clad plates, containing uranium -5 w/o zirconium 1.5 w/o niobium alloy cores and clad with Zircaloy-II, were rolled in plain carbon steel jackets, heat treated, physically evaluated, and corrosion tested. All these plates were found to be within predetermined dimensional tolerance in width, thickness, length, cladding thickness, and core distribution. Improved control of wielding variables and of the length of the seal pin projecting above the end plugs resulted in the elimination of frequently observed segmented inclusions at the seal pin interfaces.
Date: June 1965
Creator: Foote, Frank G.; Schumar, James F. & Chiswik, Haim H.
System: The UNT Digital Library
An Ultrasonic Measurement System for The Precise Determination of the Elastic Moduli of Single Crystals (open access)

An Ultrasonic Measurement System for The Precise Determination of the Elastic Moduli of Single Crystals

From Abstract: "The equipment described in this paper is based on the technique developed by McSkimin. Figure 1 shows a block diagram of the system. The oscilloscope presentation with no specimen present appears as shown in Figure 2a. At discrete frequencies, the pattern appears as shown in Figure 2b."
Date: May 1961
Creator: Renken, C. J.
System: The UNT Digital Library
Optimization of Efficiency of a Cesium Diode Converter (open access)

Optimization of Efficiency of a Cesium Diode Converter

From Introduction: "The efficiency of the converter is computed with the least possible assumptions. Thermal emissivity and the interelectrode heat-transfer coefficient are varied, and the effect on efficiency is investigated."
Date: March 1962
Creator: Sanathanan, C. K.
System: The UNT Digital Library
Irradiation of an Aluminum Alloy-Clad Ceramic Pellet-Fueled Plate (open access)

Irradiation of an Aluminum Alloy-Clad Ceramic Pellet-Fueled Plate

From Introduction: "An experiment, designated MTR-W10, was designed to determine the effects of high burnup on the cladding and fuel of an aluminum-1% nickel alloy (M-388)-clad ceramic pellet-fuelded plate if the type manufactured at Argonne for the BORAX-IV core. Conditions of irradiation were selected to allow local boiling at the high flux end of the plate at a pressure of 600 psig."
Date: May 1960
Creator: Gavin, A. P.
System: The UNT Digital Library
A Report on Some Attempts to Case Centrifugally Fuel Elements of Small Diameter (open access)

A Report on Some Attempts to Case Centrifugally Fuel Elements of Small Diameter

From Abstract: "The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated."
Date: March 1961
Creator: Yaggee, F. L.
System: The UNT Digital Library
Proceedings of the AMU-ANL Summer Study Program (open access)

Proceedings of the AMU-ANL Summer Study Program

From Introduction: "In 1954, the AEC presented the "five-year plan" for power reactor development, briefly outlined in Table I-1. The program proceeded and other reactors were added as a result of the incentives indicated in the outline."
Date: November 1962
Creator: Pearson, C. V.
System: The UNT Digital Library
Interim Report: Faret Experimental Program (open access)

Interim Report: Faret Experimental Program

From Introduction: "The Fast Reactor Test (FARET) program is part of the United States Fast Reactor Program directed toward the demonstration of breeder reactors essential to the long-range goal of utilizing fertile fuels. (1) With-in this program is the current thinking that the early construction and operation of two or three prototype nuclear power plants of the order of 250 Mw(e) will lead eventually to the construction of practical and economic full scale breeder reactors by the early 1980's. (2)"
Date: April 1963
Creator: Smaardyk, A.; Bump, T. R.; Handwerk, J. & Handwerk, J.
System: The UNT Digital Library
Transient Behavior of a Natural-Circulation Loop Operating Near The Thermodynamic Critical Point (open access)

Transient Behavior of a Natural-Circulation Loop Operating Near The Thermodynamic Critical Point

From Introduction: "Interest in utilizing natural-circulation loops to obtain results that aid in the design of some boiler and nuclear reactor coolant systems has focused attention on the dynamic behavior of such loops. Much analytical and experimental work has been done so as to permit predictions of the transient behavior of both single-phase and two-phase neutral-circulation systems. The analytical portion of the study consisted of simulating the loop by utilizing a digital computer to predict the measured transients."
Date: May 1963
Creator: Harden, Darrel G.
System: The UNT Digital Library
Heat Transfer, Flow Instability, and Critical Heat Flux For Water in a Small Tube At 200 psia (open access)

Heat Transfer, Flow Instability, and Critical Heat Flux For Water in a Small Tube At 200 psia

From Abstract: Report discussing "the effects of developing two-phase flow regimes in a constant-pressure drop system are shown in recorded traces from a fast-response flow transducer: the mass velocity decreases and transfer-surface superheat increases with increasing steam quality."
Date: June 1963
Creator: Weatherhead, R. J.
System: The UNT Digital Library
On The Steady-State Thermal Stresses in Cylindrical Fuel Pins Due to Axial Variations in Their Internal Heat-Generation Rate (open access)

On The Steady-State Thermal Stresses in Cylindrical Fuel Pins Due to Axial Variations in Their Internal Heat-Generation Rate

From Introduction: "Specifically, we shall be concerned with the case of a solid right circular cylinder of infinite axial extent, having a stress-free outer boundary, being cooled by a temperature-independent boundary conductance, and having an axial heat-generation rate of form shown in Fig. 1. The inclusion of a radial dependence proportional to I^0(r/L) is only a minor complication in solving the required heat-transfer problem and, for reference, has been included in the solution for the temperature field to be found in Section II below."
Date: December 1966
Creator: Valentin, Richard A.
System: The UNT Digital Library
Two-Phase Heat Transfer With Gas Injection Through A Porous Boundary Surface (open access)

Two-Phase Heat Transfer With Gas Injection Through A Porous Boundary Surface

From Introduction: "The purpose of this study is to investigate some of the hydrodyamic aspects of two-phase heat transfer in the lower quality range. The results of this study should contribute to a better and more thorough understanding of the processes and mechanisms affecting two-phase heat transfer, and in this way help in improving its prediction."
Date: March 1964
Creator: Kudirka, A. A.
System: The UNT Digital Library
Pictorial Studies of Molecules 1: Molecular Orbital Density Comparisons of H2, Li2, B2, C2, N2, O2, and F2 (open access)

Pictorial Studies of Molecules 1: Molecular Orbital Density Comparisons of H2, Li2, B2, C2, N2, O2, and F2

From Review of Theory: " In practice, a very close approximation to the molecular orbitals can be obtained in this way. Recent calculations of this type, utilizing analysis and computer programs developed by the author, have resulted in the determination of the molecular orbitals for a large number of diatomic molecules in the form of Eq. (2). These functions, which are thought to be very close to the Hartree-Fock (i.e., the molecular orbitals demanded by theory) result, were used in the pictorial calculations presented in this report."
Date: July 1965
Creator: Wahl, Arnold C.
System: The UNT Digital Library
XLIBIT: ANL Cross-section Library Code (open access)

XLIBIT: ANL Cross-section Library Code

From Introduction: "With the acquisition by the Laboratory of a Control Data 3600 computer in the fall of 1963, a joint reprogramming project was undertaken by the Laboratory's Applied Mathematics Division and the Control Data Corporation to develop one - and two-dimensional diffusion-theory and Sn transport-theory programs for the CDC-3600. The XLIBIT code described in this report was developed as a part of this project. XLIBIT is a CDC-3600 program designed to: 1) Prepare a cross-section library tape. 2) Modify an existing cross-section library tape. 3) Duplicate an existing cross-section library tape. 4) Print all or a portion of the cross-section data on the library tape. Punch cross-section decks for all or a portion of the data on the library tape. The decks produced are identical to those used in pertaining the tape."
Date: February 1966
Creator: Sparck, S. D.
System: The UNT Digital Library
A Study of Convective Magnetohydrodynamic Channel Flow (open access)

A Study of Convective Magnetohydrodynamic Channel Flow

Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.
Date: March 1965
Creator: Singer, Ralph M.
System: The UNT Digital Library
Self-Sustained Hydrodynamic Oscillations in a Natural Circulation Two-Phase-Flow Boiling Loop (open access)

Self-Sustained Hydrodynamic Oscillations in a Natural Circulation Two-Phase-Flow Boiling Loop

Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.
Date: August 1965
Creator: Jain, Kamal C.
System: The UNT Digital Library
Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow (open access)

Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow

Two-phase flow-regime transitions at elevated pressures for a single-component, trichloromonofluoromethane, were investigated for forced-circulation, upward flow in a vertical, rectangular conduit with internal dimensions of 0.380 by 1.050 inches.
Date: September 1965
Creator: Baker, James L. L.
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
Reactor Development Program Progress Report: March 1963 (open access)

Reactor Development Program Progress Report: March 1963

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: April 15, 1963
Creator: Adams, R. M. & Glassner, A.
System: The UNT Digital Library
Reactor Development Program Progress Report: April 1963 (open access)

Reactor Development Program Progress Report: April 1963

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: May 15, 1963
Creator: Adams, R. M. & Glassner, A.
System: The UNT Digital Library
Reactor Development Program Progress Report: November 1965 (open access)

Reactor Development Program Progress Report: November 1965

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during November 1965. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: December 27, 1965
Creator: Adams, R. M. & Glassner, A.
System: The UNT Digital Library
Reactor Development Program Progress Report: May 1966 (open access)

Reactor Development Program Progress Report: May 1966

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during May 1966. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: June 30, 1966
Creator: Adams, R. M. & Glassner, A.
System: The UNT Digital Library
Reactor Development Program Progress Report: September 1966 (open access)

Reactor Development Program Progress Report: September 1966

Report issued by the Argonne National Laboratory discussing progress made within the Reactor Development Program for September, 1966. The report includes highlights of the different project activities including plutonium utilization, fast breeder reactors, general reactor technology, advanced systems research, and nuclear safety. This report includes tables, illustrations, and photographs.
Date: October 26, 1966
Creator: Adams, R. M. & Glassner, A.
System: The UNT Digital Library