TRANSIENT HEATING OF UC FUEL ELEMENTS IN THE KEWB FACILITY (open access)

TRANSIENT HEATING OF UC FUEL ELEMENTS IN THE KEWB FACILITY

The feasibility of using the KEWB reactor as a pulsed neutron radiation source for use in studies of fuel element transient heating was studied. UC fuel rod samples were heated in the reactor. It was found that flux distribution in fuel samples could be mapped and thermal conductivity measurements for UC could be made by using fast response thermocouples distributed radially in the sample. (J. R.D.)
Date: September 1, 1959
Creator: Gardner, E.L. & Barnes, S.G.
System: The UNT Digital Library
RECYCLE OF UO$sub 2$F$sub 2$ IN THE FLUOROX PROCESS: REACTION OF UO$sub 2$F$sub 2$ WITH HYDROGEN (open access)

RECYCLE OF UO$sub 2$F$sub 2$ IN THE FLUOROX PROCESS: REACTION OF UO$sub 2$F$sub 2$ WITH HYDROGEN

The reaction of U0/sub 2/F/sub 2/ with hydrogen at 700 to 850 deg C was briefly investigated since it could constitute a major step in the recycle of U0/ sub 2/F/sub 2/ in the Fluorox process. The reaction in this temperature range proceeds according to the equation U0/sub 2/F/sub 2/ + H/sub 2/ yields U0/sub 2/ + 2 HF. Rates of the chemical reaction were not obtsined, since, with the thermogravimetric technique used, the rate-controlling process was bed diffusion. However, there is no doubt that the rate of chemical reaction is sufficiently high for the desired application. No significant amount of UF/sub 4/ was formed by the back-reaction, U0/sub 2/ + 4 HF yields UF/sub 4/ + 2 H/sub 2/0. (auth)
Date: July 1, 1959
Creator: Ferris, L.M. & Gardner, R.P.
System: The UNT Digital Library
The Determination of Chlorine in Polyurethane Plastic (open access)

The Determination of Chlorine in Polyurethane Plastic

Chlorine may be determined in polyurethane by gravimetric or spectrophotometric techniques. The sample is burned in a special combustion tube with two oxygen inlets, the products of combustion are absorbed in a solution containing sodium hydroxide and hydrogen peroxide, and the chlorine is measured either gravimetrically as silver chloride or spectrophotometrically using mercuric thiocyanate and ferric perchlorate. Eighteen determinations of cblorine in known solutions of sodium chloroacetate or perchloric acid gave an average recovery of 98.3% with a standard deviation of 2.8%. (auth)
Date: October 1, 1959
Creator: Henicksman, A. L.; VanKooten, E. H.; Gardner, R. D. & Ashley, W. H.
System: The UNT Digital Library
MECHANICAL PROPERTY AND FORMABILITY STUDIES ON UNALLOYED PLUTONIUM (open access)

MECHANICAL PROPERTY AND FORMABILITY STUDIES ON UNALLOYED PLUTONIUM

The effect of temperature and testing speed on the tension and compression properties of unalloyed plutouium was studied in the alpha , beta , gamma , and delta phases. Compressive formability data were obtained for a load of 100,000 lbs in the aforementioned phases. In addition, preliminary creep, tension impact, and torsion data for alpha -phase plutonium are reported. Extrusion constants and pressures for the beta , gamma , and delta phases were obtained. The roomtemperature tension and compression properties of the beta - and #gg-extruded plutonium were determined. Metallo graphic studies were made to determine the effect of tension, compression, and extrusion, in the indicated phases, on the microstructure of as-cast plutonium. (auth)
Date: December 1, 1959
Creator: Gardner, H.R. & Mann, I.B.
System: The UNT Digital Library
Activation Analysis Nuclear Chemical Research Radiochemical Separations. Progress Report No. 8 for November 1958-October 1959 (open access)

Activation Analysis Nuclear Chemical Research Radiochemical Separations. Progress Report No. 8 for November 1958-October 1959

Activities at the Michigan Reactor and pneumatic tube system are outlined. Various modifications including installation and operation of a "bunny" rabbit pneumatic tube system for transferring samples from laboratory to counter are described. Prelimirary investigation for design of a neutron generator for activation work is described. Modifications to the 100-channel pulse-height analyzer including addition of auxillary circuits and additioral detectors are sumnnarized. In nuclear chemistry a cyclotron bombardment to produce long-lived vanadium tracer for yield determinations in activation analysis is described. Summaries of project work which have been published on absolute (d, alpha) reaction cross sections and excitation functions, use of computers in nuclear data analysis, and research on Ir/sup 196/ are presented. Study of the gamma spectra of 33-second Kr/sup 90/, 41-second Xe/sup 139/, and some longer-lived fission product rare gases is reported and a summary of preliminary results is given. Detection of a long-lived isomer of Ag/sup 108/ in old Ag/sup 110m/ samples is reported and new values for the branching ratios of 2.4minute Ag/sup 108/ are given. Activities of the Subcommittee on Radiochemistry are summarized. Development of a radiochemical procedure by the use of amalgam exchange is reported and exchange of the elements Cd, Tl, Zn, Pb, …
Date: November 1, 1959
Creator: Maddock, R. S. & Meinke, W. W.
System: The UNT Digital Library
IGNITION BEHAVIOR AND KINETICS OF OXIDATION OF THE REACTOR METALS, URANIUM, ZIRCONIUM, PLUTONIUM, AND THORIUM, AND BINARY ALLOYS OF EACH. A Status Report (open access)

IGNITION BEHAVIOR AND KINETICS OF OXIDATION OF THE REACTOR METALS, URANIUM, ZIRCONIUM, PLUTONIUM, AND THORIUM, AND BINARY ALLOYS OF EACH. A Status Report

>The importance of prevention of fires and explosions involving uranium, zircomum, plutonium, and thorium, which are of particular interest to the nuclear energy program, made imperative the study of their ignition behavior and oxidation kinetics. Methods of measurements of ignition characteristics of uranium and zirconium were developed and used to determine the effects of variables, such as surface preparation, metallurgical history, specific area (sample size), additives to the metal, and oxygen content and presence of moisture in the oxidizing gas. The study of ignition characteristics was supported by study of the effects of similar variables on the kinetics of oxidation of uranium and zirconium and binary alloys of each. The oxidation of uranium always proceeded in two linear stages over the temperature range of 125 to 295 deg C at pressures of 20, 50, 200, and 800 mm of oxygen. The temperature dependences of both stages indicate an activation energy dependent on pressure. The presence of ten additive elements in uranium metal caused only very small effects on the oxidation. The oxidation of zirconium was independent of pressure and proceeded according to a cubic rate law over the temperature range from 400 to 900 deg C, with an activation energy …
Date: April 1, 1959
Creator: Schnizlein, J. G.; Pizzolato, P. J.; Porte, H. A.; Bingle, J. D.; Fischer, D. F.; Mishler, L. W. et al.
System: The UNT Digital Library
Tabulated Neutron Cross Sections. Part 1. 0.001-14.5 Mev. Volume 2. $sub 23$v-$sub 20$Sn (open access)

Tabulated Neutron Cross Sections. Part 1. 0.001-14.5 Mev. Volume 2. $sub 23$v-$sub 20$Sn

Tables of neutron total, elastic, inelastic, scattering, and absorption cross sections are presented for the elements V through Sn at 0.001 to 14.5 Mev. (C.J.G.)
Date: October 1, 1959
Creator: Howerton, Robert J.
System: The UNT Digital Library
TABULATED NEUTRON CROSS SECTIONS, PART 1. 0.001-14.5 MEV. VOLUME 1. $sub 1$H-$sub 22$Ti (open access)

TABULATED NEUTRON CROSS SECTIONS, PART 1. 0.001-14.5 MEV. VOLUME 1. $sub 1$H-$sub 22$Ti

Tables of neutron total, elastic, inelastic, scattering, and absorption cross sections are presented for the elements hydrogen through titanium at 0.001 to 14.5 Mev. (C.J.G.)
Date: October 1, 1959
Creator: Howerton, R. J.
System: The UNT Digital Library
Grain Refinement of Uranium by a Beta-Quench, Alpha-Anneal Process (open access)

Grain Refinement of Uranium by a Beta-Quench, Alpha-Anneal Process

None
Date: February 1, 1959
Creator: Angerman, C.L.; Huntoon, R.T. & McDonell, W.R.
System: The UNT Digital Library
POWER REACTOR FUEL REPROCESSING: MECHANICAL PHASE (open access)

POWER REACTOR FUEL REPROCESSING: MECHANICAL PHASE

An occurrence at the SRE which caused approximately 7 fuel elements to part when being pulled from the reactor complicated reprocessing, however the bulk of the elements may still be reprocessed as planned. New or reworked pants for the mechanical decladder were supplied by the fabricators for rebuilding in ORNL shops. Administrative actions dictated by budgetary considerations include reduction of UO/sub 2/ pellet order to the quantity needed this fiscal year, reduction of Mark III prototype fuel element to 12, stoppage of all work by REE Division personnel, and stoppage of all work not related to SRE fuel element reprocessing. (auth)
Date: September 1, 1959
Creator: Klima, B.B.
System: The UNT Digital Library
THE ANALYSIS OF REFRACTORY BORIDES, CARBIDES, NITRIDES, AND SILICIDES (open access)

THE ANALYSIS OF REFRACTORY BORIDES, CARBIDES, NITRIDES, AND SILICIDES

Methods are presented for the analysis of 41 refractory materials. An evaluation of the accuracy and the precision of these techniques are also given The materials studied are the borides of hafnium, molybdenum, niobiumL rhenium, tantalum, thorium, titanium, tungsten, uranium vanadium, and zirconium; the carbides of hafnium molybdenum, miobium, silicon, tantalum, thorium, titanium, tungsten, uranium, vanadium, and zircomium; the nitrides of boron, hafnium, niobium, silicon, tantalum, titanium, uranium, and zirconium; the silicides of molybdenum, rhenium, tantalum, titanium, tungsten, vanadium, and zirconium; and mixed carbides of uranium with hafnium, niobium, tantalum, or zirconium. (auth)
Date: March 1, 1959
Creator: Kriege, O.H.
System: The UNT Digital Library
Reactor Kinetics Quarterly Progress Report for January-March 1957 (open access)

Reactor Kinetics Quarterly Progress Report for January-March 1957

Investigation of the energy coefficient of radiolytic gas production for the KEWB I reactor as a function of core temperature shows the coefficient to be independent of temperaturc above about 30 C. The temperature coefficient of reactivity is found to increase markedly with temperature and reach a value of 0.031%/ C at 90 C with a core pressurc of 71 cm Hg. A void coefficient of reactivity was determined in the certral exposure tube of the reactors and is related to the void coefficient derived from the temperature coefficient measurements. Investigations of the transient power oscillations show a decrease in the period of oscillation and an increase in the damping of the oscillation with increasing reactivity input. An evaluation of the ''boron-bubble'' experiment and its extension to more complex geometries was made in conaection with the determination of ''absolute reactivity.'' This study indicated a possible solution to the difficulties involved in the experimental determination of the absolute reactivity as contrasted with the reactivity in dollars observable in kinetic experiments. A method was devised for determining the transfer function of a reactor from power fluctuations during steady operation by treating the fluctuations as the response of the system to an inherent …
Date: January 1, 1959
Creator: Remley, M.E. ed.
System: The UNT Digital Library
Annual Report of the Girl Scouts of the United States of America: 1958 (open access)

Annual Report of the Girl Scouts of the United States of America: 1958

Annual report submitted by the Girl Scouts of the United States of America to Congress describing highlights from 1958, activities, finances, organizational leadership, and other information about scouting programs.
Date: April 1, 1959
Creator: Girl Scouts of the United States of America
System: The Portal to Texas History
Reactor Kinetics: A Bibliography (open access)

Reactor Kinetics: A Bibliography

ABS>A bibliography covering the material listed in Nuclear Science Abstracts and Abstracts of Classified Reports up to July 1958 is presented. It is divided into 39 sections with author and report number indexes and a glossary of abbreviations. Each subject group has the entries by author onder, or by title (if no author listed). Each entry has a number so as to assist the location of reports from either the author or number indexes. While this biblicgraphy includes classified reports (indicated by AEC Classified), there are no classified titles. Publication dates of reports are given, when available, except where a date shows in the title, such as in progress reports. The report number index may be of special value to those researchers who desire all of one company's reports on this subject. (auth)
Date: November 1, 1959
Creator: Bloomfield, M. & Bennet, F. G.
System: The UNT Digital Library
SANDIA CORPORATION BIBLIOGRAPHY--RADIATION EFFECTS (open access)

SANDIA CORPORATION BIBLIOGRAPHY--RADIATION EFFECTS

None
Date: December 1, 1959
Creator: unknown
System: The UNT Digital Library