On the Use of a Modified Radial Distribution Analysis for Indexing Powder Patterns (open access)

On the Use of a Modified Radial Distribution Analysis for Indexing Powder Patterns

None
Date: June 25, 1962
Creator: Berndt, A. F.
Object Type: Report
System: The UNT Digital Library
A Needle in a Haystack (open access)

A Needle in a Haystack

Abstract: "Production of [rho]'s and [omega]'s in [pi]- + p and p + [letter p with a bar over it] interactions is discussed. The [rho] is presumably a J = 1-, 1 = 1 state and thus can decay into 2[pi]'s via a strong coupling. The [omega] is probably J = 1-, 1 = 0 which can also decay into 2[pi]'s via electromagnetic coupling. A theoretical description of this situation is presented in terms of coupled time-dependent Schroedinger equations which mix [rho] and [omega] states that are assumed to be isotopically pure at the time of production. The interference between the two resonances was found to have the effect of extending the 2[pi] spectrum toward the [omega] mass."
Date: May 25, 1962
Creator: Bernstein, J. & Feinberg, Gerald, 1933-1992
Object Type: Report
System: The UNT Digital Library
NPR Physics Startup Testing Program (open access)

NPR Physics Startup Testing Program

The New Production Reactor, as compared to existing Hanford reactors, employs new and unique design concepts. To properly evaluate these design concepts and their effects on reactor operations, nuclear safety, and reactor life, a comprehensive testing program is planned; this program, with its objectives and restrictions, is discussed in this report. It has been developed along the same line as the C and K Reactors test, programs, and is expected to require a total time of 6--8 weeks of round-the-clock testing. This estimate includes fuel loading time, but does not include time allotments for engineering acceptance tests prior to power operation nor does it include any of the time necessary for engineering and physics tests during the extensive power ascension program. The main body of this report is presented in three parts. The first section describes startup hazards and restrictions, reactor and component safety provisions prior to loading, and the itemized listing of quantities to be measured. The second includes preliminary material and plant conditions and a brief description of the individual tests. The third section (the Appendix), written in procedure language, comprises a rather detailed description of each individual test on a tentative basis; final test details and procedures, …
Date: April 25, 1962
Creator: Bowers, C. E.
Object Type: Report
System: The UNT Digital Library
Conceptual Design for a 75 MWE Mixed Spectrum Superheating Reactor Power Plant (open access)

Conceptual Design for a 75 MWE Mixed Spectrum Superheating Reactor Power Plant

The design, performance, and cost information on the nuclear portion of the Mixed Spectrum Superheater power plant are emphasized. The research and development programs required to ensure plant feasibility are also presented. The nuclear steam supply system, reactor auxiliary systems, radiation control systems, control and instrumentation, special test instrumentation, plant operation and maintenance, steam cycle, turbine plant, general service systems, preliminary safeguards considerations, expansion of plant power output to 150 Mw(e), and MSSR critical experiment are described. (M.C.G.)
Date: February 25, 1962
Creator: Brynsvold, G. V.; Hikido, K.; Reynolds, A. B. & Riley, D. R.
Object Type: Report
System: The UNT Digital Library
Final report: Irradiation performance of a coextruded, Zircaloy-2-clad three-rod cluster fuel elements, PT-IP-186-A (open access)

Final report: Irradiation performance of a coextruded, Zircaloy-2-clad three-rod cluster fuel elements, PT-IP-186-A

One of the early candidate fuel elements for N Reactor use was the coextruded, Zircaloy-2-clad seven-rod cluster. As part of the program of evaluating the seven-rod cluster geometry, three-rod cluster fuel elements, two and three feet long, were irradiated. These long cluster fuel elements were irradiated to determine the distortion (or sag) which might occur at the center of the unsupported length during irradiation. Two three-rod clusters made up of 0.630 inch diameter rods, containing natural uranium cores were irradiated in KER Loop 3. The rods of one cluster were three feet long; the rods of the other were two feet long. The three-feet long rods were supported at their ends and at their midlengths, the two-feet long rods only at their ends. During the irradiation, the maximum core temperature was 435 C. The fuel elements were discharged from the loop after they had reached an exposure of 1400 MWD/T. Following the discharge, the fuel elements were visually examined in the KE view pit. No sag was observed in any of the rods. The test demonstrated that two- and three-feet long rod cluster fuel elements can be irradiated without appreciable sag occurring in the rods.
Date: July 25, 1962
Creator: Call, R. L.
Object Type: Report
System: The UNT Digital Library
Low exposure irradiation of an enriched seven-rod cluster in KER Loop 1, PR-IP-246-A: Final report (open access)

Low exposure irradiation of an enriched seven-rod cluster in KER Loop 1, PR-IP-246-A: Final report

One of the early candidate fuel elements for the N Reactor was the seven-rod cluster fuel element. An objective of the program to determine the suitability of the seven-rod cluster fuel element for N Reactor use was to evaluate the irradiation performance of coextruded, Zircaloy-2-clad, seven-rod cluster fuel elements over a range of exposures from low exposures to high exposures. This report describes the irradiation testing of an enriched seven-rod cluster fuel element which was irradiated to 520 MWD/r.
Date: July 25, 1962
Creator: Call, R. L.
Object Type: Report
System: The UNT Digital Library
Primary Quantum Conversion in Photosynthesis (open access)

Primary Quantum Conversion in Photosynthesis

None
Date: August 25, 1962
Creator: Calvin, Melvin & Androes, G. M.
Object Type: Article
System: The UNT Digital Library
Test of German Underground Personnel Shelters (open access)

Test of German Underground Personnel Shelters

The objective of Project 30.7 was to investigate the predicted behavior of German underground personnel shelters, equipment, and certain instrumentation. Data obtained will be used for evaluation and improvement of present design criteria.
Date: June 25, 1962
Creator: Cohen, Edward & Bottenhofer, A.
Object Type: Report
System: The UNT Digital Library
Measured vs calculated river {Delta}T (open access)

Measured vs calculated river {Delta}T

River temperature traverse data within and just the plant boundary are quite limited. For this report, traverse temperatures were calculated by first averaging the depth measurements vertically at each traverse point, and then weighing the average for the cross section by the depth at each point and the span between points. Calculated {Delta} T`s were determined by dividing the total reactor power level above the traverse line by the river flow, with the appropriate factor to obtain the correct units. No attempt has been made to apply corrections for atmospheric effects or the diurnal cycle.
Date: October 25, 1962
Creator: Corley, J. P.
Object Type: Report
System: The UNT Digital Library
Study of Metal-1.10-Phenanthroline Complex Equilibria by Potentiometric Measurement (open access)

Study of Metal-1.10-Phenanthroline Complex Equilibria by Potentiometric Measurement

Technical report. From Abstract : "The silver-1,10-phenanthroline system has been studied and the stability constants determined for the 1:1 and 2:1 complexes using the silver electrode. This known system was then used to study the complexes of 1,10-phenanthroline with other metals. The log βn values found for the over-all stoichiometric stability constants are as follows: Ag, 5.02, 12.07; Mn, 3.88, 7.04, 10.11; Cd, 5.93, 10.52, 14.30; Zn, 6.83, 12.05, 16.92. The stoichiometric stability constants determined for copper are log k2 = 6.42 and log k2k3 = 11.05."
Date: October 25, 1962
Creator: Dale, John M. & Banks, Charles V.
Object Type: Report
System: The UNT Digital Library
Army PWR Support and Development Program Six Months Summary Report : October 1, 1961 - March 31, 1962 (open access)

Army PWR Support and Development Program Six Months Summary Report : October 1, 1961 - March 31, 1962

Abstract: Progress is reported on research and development tasks under the Program Plan for Engineering Support and Development of Army Pressurized Water Reactor Power Plants, Contract AT(30-1)-2639, during the six months' period October 1, 1061 to March 31, 1962.
Date: May 25, 1962
Creator: Dixon, M. H.
Object Type: Report
System: The UNT Digital Library
Geology of core hole WP-4 Tatum dome, Lamar County, Mississippi. Technical letter: Dribble-19 (open access)

Geology of core hole WP-4 Tatum dome, Lamar County, Mississippi. Technical letter: Dribble-19

None
Date: April 25, 1962
Creator: Eargle, D.H.
Object Type: Report
System: The UNT Digital Library
Specifications and Fabrication Procedures for Type 3 Neutron Absorber Sections (open access)

Specifications and Fabrication Procedures for Type 3 Neutron Absorber Sections

The specification contains information concerning the material, process, and product requirements to be met by the fabricator. (J.R.D.)
Date: April 25, 1962
Creator: Edgar, E. C. & Clayton, H. R.
Object Type: Report
System: The UNT Digital Library
Color Production From Energetic Ions Impinging On Metals (open access)

Color Production From Energetic Ions Impinging On Metals

It has been observed that energetic gaseous ions mark their region of impingement on certain metals in color. Under identical conditions of bombardment, multicharged ions of the same gas mark their impact areas with different colors. The colors are sensitive to the type and energy of the ion as well as to the metal bombarded. These colors may result from reflections from thin films formed by reactions at the target. Because the colors indicate that thicker films are produced with increased ion energy, ion penetration depth as predicted by theory is compared with the depth indicated by the colors observed.
Date: June 25, 1962
Creator: Ehlers, Kenneth W.
Object Type: Report
System: The UNT Digital Library
Summary of HRT Run 25 (open access)

Summary of HRT Run 25

Run 25 was the final period of power operational of the HRT. The reactor was operated for periods of 62, 8, 52, and 80 hours at 5 Mw with no outward indication of fuel and core and blanket average temperatures of 270 and 230 deg C, respectively. The uranium concentration in the was 1.7 to 2.0 g U/kg D/sub 2/O. Longer periods of operation were prevented by mechanical difficulties, notably with the fuel feed pump. While the reactor was subcritical after the last of the above runs, the upper patch in the core tank wall became dislodged, allowing greater core-to-blanket mixing. The resultant blanket uranium concentration was 2.9 g U/kg D/sub 2/O. The reactor was subsequently operated at April 28, 1961. The experiment was operated at high temperature for a total of 10,866 hours. The system was critical for a total of 8,841 hours and produced 16,295 Mwhours of power. The fuel, heavy water, and some corrosion specimens were recovered, and the reactor was stored in an assembled state. (auth)
Date: July 25, 1962
Creator: Engel, J. R.; Bauman, H. F.; Buchanan, J. R.; Haubenreich, P. N.; Piper, H. B. & Richardson, D. M.
Object Type: Report
System: The UNT Digital Library
GRAPHITE-STAINLESS STEEL COMPATIBILITY STUDIES (open access)

GRAPHITE-STAINLESS STEEL COMPATIBILITY STUDIES

S>The compatibility of type 304L stainless steel in intimate contact with graphite is being studied as a function of temperature and contact pressure. This study is an outgrowth of materials compatibility problems in present and advanced gas-cooled reactors, where structural members in direct contact with graphite provide the possibility of both carburization and self-welding. Initial studies were concerned with surface reactions in the absence of gaseous contaminants under a vacuum of 10/sup -6/ mm Hg at 540 to 705 deg C. Stainless steel specimens are pretreated to provide three surface conditions: H/sub 2/- fired, preoxidized, and Cu-plated. Surface contact pressures ranged from 0 to 10,000 psi. Test results are presented which establish the lower temperature limit for significant diffusion between graphite and stainless steel at approximately 60O deg C. Above this temperature, diffusion between untreated or H2-fired stainless steel surfaces was found to effect complete bonding of the two materials at contact pressures as low as 500 psi. Bonding was effectively prevented by the presence of either an oxide film or a Cu plate at temperatures up to 700 deg C. Where bonding occurred, diffusion rates measured for C in stainless steel were comparable with those reported for stainless steel …
Date: September 25, 1962
Creator: Fleischer, B.; DeVan, J. H. & Coobs, J. H.
Object Type: Report
System: The UNT Digital Library
Hydrologic and Geologic Studies for Project Gnome: Progress Report (open access)

Hydrologic and Geologic Studies for Project Gnome: Progress Report

From introduction: The broad objectives of the Survey's program are to provide the basic geologic and geophysical information needed to define the pre- and post-shot geologic and physical properties of salt and other rocks affected by the explosion. To provide geologic and hydrologic information on the pre- and post-shot hydrologic conditions at the Gnome site and surrounding region.
Date: September 25, 1962
Creator: Geological Survey (U.S.)
Object Type: Report
System: The UNT Digital Library
Technical specifications, Hanford production reactors (open access)

Technical specifications, Hanford production reactors

These technical specifications are applicable to the eight operating production reactor facilities, B, C, D, DR, F, H, KE, and KW. Covered are operating and performance restrictions and administrative procedures. Areas covered by the operating and performance restrictions are reactivity, reactor control and safety elements, power level, temperature and heat flux, reactor fuel loadings, reactor coolant systems, reactor confinement, test facilities, code compliance, and reactor scram set points. Administrative procedures include process control procedures, training programs, audits and inspections, and reports and records.
Date: June 25, 1962
Creator: Gilbert, W. D.
Object Type: Report
System: The UNT Digital Library
The Deflecting Mode in the Circular Iris-Loaded Waveguide of a RF Particle Separator (open access)

The Deflecting Mode in the Circular Iris-Loaded Waveguide of a RF Particle Separator

The rf particle separator, proposed in 1959 by W.K.H. Panofsky and now in preparation for the Brookhaven Alternating Gradient Synchrotron, required a rf structure which gives a transverse impulse to a passing relativistic particle. In order to produce an accumulative transverse deflection of a traveling charged particle with an electromagnetic field, it is necessary that the field contains a synchronous component and in principle, waveguides and cavities are equivalent with respect to the particle dynamics. It was pointed out by H.G. Hereward, that the electric and magnetic deflection of a transverse electric mode (i.e., with no electric field component parallel to the direction of the particle velocity) cancel exactly at all particle velocities. The deflecting force of a transverse magnetic mode on a synchronous particle with the velocity v is proportional to the factor 1-(v/c)2 and vanishes therefore in the case of relativistic particles.
Date: October 25, 1962
Creator: Hahn, H.
Object Type: Report
System: The UNT Digital Library
THE DEFLECTING MODE IN THE CIRCULAR IRIS-LOADED WAVEGUIDE OF A RF PARTICLE SEPARATOR. Internal Report (open access)

THE DEFLECTING MODE IN THE CIRCULAR IRIS-LOADED WAVEGUIDE OF A RF PARTICLE SEPARATOR. Internal Report

An analysis is presented of the deflecting mode in an iris-loaded synchrotron waveguide which is not based on the concept of TE and TM modes as generating fields. The solutions employed are derived from the transverse components of the electric and magnetic Hentzian factors. Their use avoids the singnlarities in the field expressions for phase velocities equal to that of light, which must occur with TE and TM modes. The fundamental properties of the hybrid solutions are exposed. The lowest mode of the hybrid group is the desired deflecting mode. The exact relation between frequency, phase velocity, and geometry of the structure can be derived for the deflecting mode in the form of an infinite determinant. Transverse and hybrid solutions are tabulated. (J.R.D.)
Date: October 25, 1962
Creator: Hahn, H.
Object Type: Report
System: The UNT Digital Library
Molecular Spectra and Structure of the Compound, AlH3-2N(CH3)3 (open access)

Molecular Spectra and Structure of the Compound, AlH3-2N(CH3)3

This technical report discusses an infrared study of AlH3-2N(CH3)3 while the compound was in its gas phase. This investigation was then extended to include the Raman spectrum observed in liquid trimethylamine.
Date: May 25, 1962
Creator: Heitsch, C. W. & Kniseley, R. N.
Object Type: Report
System: The UNT Digital Library
Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Ninth Quarterly Progress Report July 1962 - September 1962 (open access)

Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Ninth Quarterly Progress Report July 1962 - September 1962

The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor (VBWR) and other facilities to improve the technological limits of boiling water reactors.
Date: October 25, 1962
Creator: Howard, C. L.
Object Type: Report
System: The UNT Digital Library
Hallam Nuclear Power Facility, Preoperational Test Interim Report Dry Excess Loading (open access)

Hallam Nuclear Power Facility, Preoperational Test Interim Report Dry Excess Loading

A test to obtain data for use in determining the reactivlty wohh of Na in the Hallam reactor core is described. The test is designed to obtain information on the dry temperature coefficient of reactivity and to train operators. An evaluation of results is included. (J.R.D.)
Date: February 25, 1962
Creator: Kempt, H. C. & Corcoran, W. P.
Object Type: Report
System: The UNT Digital Library
XNJ140E Nuclear Turbojet, Section 5, Shield; Section 6, Turbomachinery; Section 7. Control System (open access)

XNJ140E Nuclear Turbojet, Section 5, Shield; Section 6, Turbomachinery; Section 7. Control System

This volume is one of twenty-one summarizing the Aircraft Nuclear Propulsion Program of the General Electric Company.
Date: May 25, 1962
Creator: Layman, D. C.
Object Type: Report
System: The UNT Digital Library