Slowing-Down Spectra of Neutrons in Heavy Water and Light Water Mixtures (open access)

Slowing-Down Spectra of Neutrons in Heavy Water and Light Water Mixtures

The slowing down spectra of neutrons were obtained for heavy water, light water, and mixtures of heavy water and light water. It was assumed that fission neutrons are produced uniformly throughout an infinite moderator and the only process considered was elastic scattering, spherically symmetric in the center-of-mass system. The (n,2n) reaction with the deuterium nucleus and absorption were assumed negligible. The average transfer cross section, fast diffusion coefficient, the slowing down area, and average velocity ratio were obtained for two-group calculations using the epithermal spectra. (auth).
Date: October 1, 1961
Creator: Duncan, M. Elaine; Hines, K. C. (Kenneth Charles), 1926-2005 & Pollard, J. P. (John Percival)
Object Type: Report
System: The UNT Digital Library
Status of Uranium Exploration in Turkey (open access)

Status of Uranium Exploration in Turkey

Field evaluations made of uranium deposits located in and near southwestern Turkey
Date: October 1961
Creator: Kratchman, Jack
Object Type: Report
System: The UNT Digital Library
A Theoretical Consideration Of Asymmetric Heat Flow At The Interface Of The Dissimilar Metals (open access)

A Theoretical Consideration Of Asymmetric Heat Flow At The Interface Of The Dissimilar Metals

Several investigators have found that the resistance to heat transfer at certain metal-metal interfaces is dependent upon the direction of heat flow across these interfaces. This paper shows that such a phenomenon can be explained by application of the theory of heat conduction in the solid state.
Date: October 1961
Creator: Moon, Joon Sang & Keeler, R. N.
Object Type: Report
System: The UNT Digital Library
Las Vegas Area (ARMS-II) (open access)

Las Vegas Area (ARMS-II)

From Abstract: "An Aerial Radiological Measuring Survey (ARMS) of the Las Vegas area was made for the Civil Effects Test Operations, Division of Biology and Medicine, U.S. Atomic Energy Commission, by Edgerton, Germeshausen & Grier, Inc., between May 21 and June 23, 1961. The survey was part of a nationwide program to measure present environmental levels of gamma radiation. Approximately 6000 traverse miles were flown, at an attitude of 500 ft above the ground, in a 100-mile square centered near Las Vegas. The EG&G ARMS-II instrumentation was used in the survey."
Date: October 1961
Creator: Guillou, R. B.; Hand, J. E. & Borella, H. M.
Object Type: Report
System: The UNT Digital Library
Design Criteria for Irradiated Vessels Task 6.0 Summary Report (open access)

Design Criteria for Irradiated Vessels Task 6.0 Summary Report

Abstract: This technical report presents design criteria to prevent the brittle fracture of ferritic reactor vessels that cold occur as a result of the rise in NDT caused by fast neutron irradiation. The criteria require that maximum principal stress in the vessel does not exceed 18 percent of yield stress at temperatures below NDT + 60 degree F. Under certain conditions the allowable stress may be based on the irradiated yield stress. A discussion of brittle fracture and an explanation of the criteria are included.
Date: September 29, 1961
Creator: McLaughlin, D. W.
Object Type: Report
System: The UNT Digital Library
Radioactivation Analysis (open access)

Radioactivation Analysis

The development of nuclear reactors and other sources of nuclear particles has provided the analyst with a new method which has been successfully applied to the determination of microgram and even submicrogram quantities of many elements. In this method, known as "radioactivation analysis," the element to be determined is "activated" through some type of nuclear reaction which produces a radioactive isotope of the element. Since the radioisotope produced decays with its own characteristic radiation and half-life, it is possible, through radiochemical measurements following radioactivation, to devise a method of analysis which is very specific for particular elements. Whenever necessary, the radioisotope is separated by chemical means and its radioactivity is then measured by some type of radiation counter.
Date: September 22, 1961
Creator: Leddicotte, G. W.
Object Type: Report
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report, May 31, 1961 (open access)

Chemical Technology Division Annual Progress Report, May 31, 1961

Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.
Date: September 21, 1961
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Object Type: Report
System: The UNT Digital Library
Feasibility Study of a New Mass Flow System : Quarterly Report No. 5 Covering the Period from June 1, 1961 to August 31, 1961 (open access)

Feasibility Study of a New Mass Flow System : Quarterly Report No. 5 Covering the Period from June 1, 1961 to August 31, 1961

This is the fifth quarterly report that documents a system of mass flow that can record measurements of homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, additionally considering pressure drops, measuring external to the flow, ruggedness and reliability.
Date: September 20, 1961
Creator: Haffner, J. W. & Genthe, William K.
Object Type: Report
System: The UNT Digital Library
Conceptual design of an in-pile package loop for sodium-cooled thermal reactor fuel testing (open access)

Conceptual design of an in-pile package loop for sodium-cooled thermal reactor fuel testing

Report issued by the APDA over a design study "of a facility for testing sodium-cooled thermal reactor fuel assemblies in the Advanced Test Reactor" (p. 5). The results are presented and discussed. This report includes tables, and illustrations.
Date: September 15, 1961
Creator: Blessing, W. G.
Object Type: Report
System: The UNT Digital Library
Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System (open access)

Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System

Abstract: The design and application of two computers for the HNPF protective system is discussed.
Date: September 15, 1961
Creator: Schlein, H.
Object Type: Report
System: The UNT Digital Library
Tables of Chemical Kinetics : Homogeneous Reactions (Supplementary Tables) (open access)

Tables of Chemical Kinetics : Homogeneous Reactions (Supplementary Tables)

From Preface: "A brief description of the method used in compiling these tables and the limitation of coverage is given in the preface to Supplement 1. A description of the numbering system used is classifying reactions for the tables is given in Supplement 2. The present supplement contains information pertaining to Substitution, Exchange and Elimination reaction types. It is not complete as still more material falling groups is being prepared."
Date: September 15, 1961
Creator: United States. Bureau of Standards.
Object Type: Report
System: The UNT Digital Library
Comparison of Radiation-Induced Graft Copolymerization Untilizing Electron Accelerators and Isotope Sources as Radiation Initiators (open access)

Comparison of Radiation-Induced Graft Copolymerization Untilizing Electron Accelerators and Isotope Sources as Radiation Initiators

"A comparison of grafting to two thicknesses of polypropylene film is made using isotope and electron accelerator initiation. The results indicate that the grafting of methacrylic acid: styrene to polypropylene is mainly a surface reaction."
Date: September 12, 1961
Creator: Odian, George; Oliver, William F. & Pierre, Karl
Object Type: Report
System: The UNT Digital Library
The Design, Installation, and Testing of the Gas-Cooled Reactor UOâ‚‚ Irradiation Experiment at the NRTS (open access)

The Design, Installation, and Testing of the Gas-Cooled Reactor UOâ‚‚ Irradiation Experiment at the NRTS

Report regarding sixteen experiments performed with a miniature re-entrant gas loop. Includes design problems and difficulties encountered, as well as their solutions.
Date: September 8, 1961
Creator: Porter, E. H.
Object Type: Report
System: The UNT Digital Library
Hazards Evaluation of the SM-1 Penetrated Gasket (open access)

Hazards Evaluation of the SM-1 Penetrated Gasket

Abstract: This technical report describes the as-constructed SM-1 penetrated gasket designed for SM-1 Core and Flow Instrumentation (Task XIV). This report supplements APAE No. 79, The Summary Hazards Report for Task XIV, and evaluates the effects of a postulated failure of this gasket. The effects of failure on the Maximum Credible Accident are determined and conclusions and recommendations for the use of this gasket are made.
Date: September 8, 1961
Creator: Coombe, J. R.; Gebhardt, F. G. & James, B.
Object Type: Report
System: The UNT Digital Library
International Practical Temperature Scale of 1948: Text Revision of 1960 (open access)

International Practical Temperature Scale of 1948: Text Revision of 1960

Report is a text revision of the International Temperature Scale of 1948; the numerical values of temperatures remain the same. The adjective "Practical" was added to the name by the International Committee on Weights and Measures. The scale continues to be based upon six fixed and reproducible equilibrium temperatures to which values have been assigned, and upon the same interpolation formulas relating temperatures to the indications of specified measuring instruments. Some changes have been made in the text to make the scale more reproducible than its predecessor. The triple point of water, with the value 0.01 ºC replaces the former ice point as a defining fixed point of the scale. It is also recommended that the zinc point, with the value 419.505 ºC, be used instead of the sulfur point. The recommendations include new information that has become available since 1948.
Date: September 8, 1961
Creator: Stimson, H. F.
Object Type: Report
System: The UNT Digital Library
Steady State and Transient Thermal and Hydraulic Analysis of SM-2 Termination Report (open access)

Steady State and Transient Thermal and Hydraulic Analysis of SM-2 Termination Report

Abstract: Thermal characteristics of the SM-2 core were analyzed at steady state and loss of flow conditions. For steady state operation, the steady state code STDY-3 was used. For transients during a loss of flow accident, ART-02, a one-dimensional code, was used. This analysis indicates the SM-2 core is safe from burnout under steady state operation at design power level (28 tMW) because (1) no nucleate boiling exists, and (2) the minimum burnout ratio is above 2.0. The core is safe from burnout under loss of flow transient because the minimum burnout ratio in the hottest element channel of 1. 82 is above the minimum design criteria of 1. 5.
Date: September 8, 1961
Creator: Segalman, I. & Bradley, P. L.
Object Type: Report
System: The UNT Digital Library
Consolidated Edison Thorium Reactor:  Core Assembly Physics and Zero Power Tests Report (open access)

Consolidated Edison Thorium Reactor: Core Assembly Physics and Zero Power Tests Report

Results of zero power tests to confirm the nuclear design of the Consolidated Edison Thorium Reactor Core are presented. The maximum core reactivity, control rod worths, and power distribution were measured.
Date: September 1961
Creator: Edlund, Milton C. (Milton Carl), 1924-; Ball, R. M.; Deddens, J. C. & Flickinger, R. F.
Object Type: Report
System: The UNT Digital Library
Consumers Baffle Two-Phase Air-Water Flow Tests in a One-Fifth Scale Model (open access)

Consumers Baffle Two-Phase Air-Water Flow Tests in a One-Fifth Scale Model

Tests in a one-fifth scale clear plastic model were conducted to investigate the flow characteristics of the asymmetrical riser configuration in the Consumers Big Rock power plant.
Date: September 1961
Creator: Swan, C. L.
Object Type: Report
System: The UNT Digital Library
Data Telemetry Package Powered by Strontium-90 Fueled Generator: Final Report (open access)

Data Telemetry Package Powered by Strontium-90 Fueled Generator: Final Report

From foreword: This report is divided into two parts: Part A covers the data telemetry package used for the transmission of weather station data, and Part B covers the generator which supplies power to the data telemetry package.
Date: September 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Design, Fabrication, and Irradiation of Superheat Fuel Element SH-4B in VBWR (open access)

Design, Fabrication, and Irradiation of Superheat Fuel Element SH-4B in VBWR

From abstract: "The design, fabrication, and irradiation results are described for a 0.028 inch thick 304 stainless clad fuel element (SH-4B) exposed in the Vallecitos Boiling Water Reactor loop under superheat conditions."
Date: September 1, 1961
Creator: Spalaris, C. N.; Boyle, R. F.; Evans, T. F. & Esch, E. L.
Object Type: Report
System: The UNT Digital Library
Extraction of Beryllium by Triisooctylamine : the Effect of the Anionic Complexing Agent (open access)

Extraction of Beryllium by Triisooctylamine : the Effect of the Anionic Complexing Agent

The extraction of beryllium by triisooctylamine is measured over the pH range from 1 to 10, in the presence of malonic, maleic, succinic, phthalic, and salicylic acids. Values are obtained for the stability constants of the various metal-acid complexes by potentiometric titration. The degree of extraction is dependent on the abundance of the anionic complex present in the aqueous phase and this is in turn dependent on the strength of the corresponding acid and the stability of the complex. (auth).
Date: September 1, 1961
Creator: De Bruin, H. J.; Kairaitis, D. & Temple, R. B.
Object Type: Report
System: The UNT Digital Library
Failure Test of a Double Chambered NaK-Filled Irradiation Capsule (open access)

Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.
Date: September 1961
Creator: Kosut, B. S.; Leggett, R. D. & Marshall, R. K.
Object Type: Report
System: The UNT Digital Library
Hazards Report for Insertion of the PM-1-M-2 Element in the SM-1 Core II (open access)

Hazards Report for Insertion of the PM-1-M-2 Element in the SM-1 Core II

Abstract: This technical report describes the Martin Co. PM-1-M-2 test element and analyzes the potential hazard incurred by its inclusion in the SM-1 Core II. A nuclear analysis develops power distributions and reactivity effects. Hydraulic and thermal analyses develop anticipated burnout heat flux ratios. An evaluation of the risk involved with the inclusion of this element is presented. In view of the narrow margin by which the PM-1-M-2 test element meets the minimum burnout ratios as defined by Alco Products, Inc., it is recommended that if time permits that critical facility design verification be accomplished. The PM-1-M-2 test element meets the minimum requirements for insertion in SM-1 Core II and in view of the importance of this element to the PM-1 and PM-3A program, should be considered for insertion.
Date: September 1, 1961
Creator: Coombe, J. R.; Scoles, J. F.; Brondel, J. O. & Lee, D. H.
Object Type: Report
System: The UNT Digital Library
Interim Report on Geologic Investigations of the U12b Tunnel System, Nevada Test Site, Nye County, Nevada (open access)

Interim Report on Geologic Investigations of the U12b Tunnel System, Nevada Test Site, Nye County, Nevada

From introduction: This report contains part of the geologic information obtained from investigations conducted by the USGS on behalf of the AEC to determine the geologic environment of the underground test sites at Nevada Test Site.
Date: September 1961
Creator: Dickey, D. D. & Emerick, W. L.
Object Type: Report
System: The UNT Digital Library