30 Matching Results

Search Results

Results: 1 - 24 next
open access

Fuel Enrichment for the Enrico Fermi Reactor

Description: Report issued by the APDA over fuel enrichment processes at the Enrico Fermi Atomic Power Plant. As stated in the introduction, "the results that directly apply to the determination of the enrichment will be given" (p. 6). This report includes tables, and illustrations.
Date: March 12, 1959
Creator: Garelis, Edward
Partner: UNT Libraries Government Documents Department
open access

Development and Evaluation of High-Temperature Tungsten Alloys : Summary Report

Description: Abstract: "Tungsten-rich alloys, developed for use at temperatures up to 2000F, exhibit ductility, fabricability and joinability not found in commercially-available materials. An envelope type of microstructure was produced in compositions containing at least 90 wt% tungsten by liquid-phase sintering of cold-pressed powders in hydrogen. At room temperature the alloys could be rolled extensively, and tensile elongations up to 25% were noted. Strength properties of a W-Ni-Fe base were improved by… more
Date: November 12, 1959
Creator: Holtz, F. C. & Van Thyne, R. J.
Partner: UNT Libraries Government Documents Department
open access

Flow conditions at outlet fittings of existing Hanford reactors

Description: This report records the basis underlying the decision already reached to recommend a change of process tube fittings at B, D, F, DR and H reactors, and also proposes for consideration a change in the devices for monitoring effluent water temperature.
Date: November 12, 1959
Creator: McLenegan, D. W.
Partner: UNT Libraries Government Documents Department
open access

Physics and Instrument Research and Development Operation. Monthly report, April 1959

Description: Areas covered in this report are as follows: nuclear safety in the Fuel Preparation Dept.; studies related to the present production reactors; studies related to future production reactors; studies related to separation plants; studies form the neutron cross section program; reactor development (gas cooled reactor program and test reactor operations); and biology and medicine.
Date: May 12, 1959
Creator: Gast, P. F.
Partner: UNT Libraries Government Documents Department
open access

Radiometallurgical examination of direct cast core fuel elements, PT-IP-93, (RM-318)

Description: This report discusses two of the direct cast core I & E fuel elements irradiated in C Reactor under PT-IP-93 which were received at the Radiometallurgy Laboratory for examination during July 1959. One of the elements was badly warped and distorted while the other of the same series had remained relatively unchanged. Both pieces had received an average exposure of 689 MWD/T. Warp and diameter measurements show that the one element had warped approximately .040 in. and had become distorted in two… more
Date: November 12, 1959
Creator: Teats, R.
Partner: UNT Libraries Government Documents Department
open access

Flow tests of J-pigtail assemblies for H-Reactor

Description: Experiments were conducted to determine the relative flow characteristics of J-pigtail adapters supplied by Lampson Products Co., Seattle.
Date: November 12, 1959
Creator: Waters, E. D.
Partner: UNT Libraries Government Documents Department
open access

ORBIT DYNAMICS IN THE SPIRAL-RIDGED CYCLOTRON

Description: Formulas are derived for the equilibrium orbit, isochronous condition, vertical and horizontal betatron frequencies, and for the effects of the 3/3 radial resonance in a three-fold geometry. The magnetic field is represented by a Fourier series in azimuth with amplitudes expanded in a Taylor series about the reference radius. The form is such that the various parameters may be deduced from an arbitrary set of field measurements in the median plane and the results obtained by direct substitution… more
Date: January 12, 1959
Creator: Smith, Lloyd & Garren, Alper A.
Partner: UNT Libraries Government Documents Department
open access

Room Temperature Water Studies of the Conical Bottom Slurry Core Vessel

Description: Water studies were performed on the conical bottom, bottom-polar inlet, core vessel to provide design information for the high-pressure model being installed in the 300SM loop. Maximum heat transfer coefficients are obtained in the conical portion of the core vessel when the inlet nozzle is inserted into the core up to the point of extension of the imaginary continuation of the top hemisphere. The flow rate in the by-pass of the 300SM loop was calculated to be 9.5to 11 gpm (7to 8 ft/ sec). The … more
Date: January 12, 1959
Creator: Wiehner, R. P.
Partner: UNT Libraries Government Documents Department
open access

Thorex pilot plant corrosion studies: 1. corrosion of types 304l and 309SCb stainless steel during production and development periods.

Description: The corrosion behavior of types 304L and 309SCb stainless steel was examined during the production and first half of the development periods of Thorex pilot plant operation between December 15, 1954 and November 10, 1955. The process vessels in which corrosion data were obtained included the batch dissolver tank the feed adjustment tank the AP catch tank and the BT vapor separator. There was no significant difference between the corrosion resistance of the two alloys in any of the environments.… more
Date: May 12, 1959
Creator: English, J. L.
Partner: UNT Libraries Government Documents Department
open access

A PRELIMINARY STUDY OF THE NUCLEAR STABILITY OF FLUIDIZED BED REACTORS

Description: A preliminary study was made of the nuclear stability of reactors in which particles containing U/sup 233/ and Th/sup 232/ are fluidized by liquid water. D/sub 2/O moderated reactors were found to be least sensitive to changes in bed height at thorium concentrations in the range 80 to 120 g/liter, H/sub 2/O reactors in the rarnge 1500 io 2400 g Th/ liter, and mixed H/sub 2/O-D/sub 2/O reactors at thorium concentrations between those for pure moderators. A reactor operated at the thorium concent… more
Date: January 12, 1959
Creator: Benumof, R. & Rosenthal, M.W.
Partner: UNT Libraries Government Documents Department
open access

A Method for Determining the Optimum Dimensional Parameters of a Scalloped Channel So as to Minimize Fuel-Element Bowing in a Septafoil Arrangement

Description: The use of a scalloped cross-sectionsl coolant channel has been suggested as a possible solution of the fuel-element bowing problem inherent in the septafoil type of geometry. Using simplified assumptions, a method has been developed for calculating the red spacing and scallop size necessary to produce equal average fuel-element surface temperatures in the central and peripheral regions of the coolant flow channel at the mid-section of each fuel-red cluster under a given set of reactor flow con… more
Date: June 12, 1959
Creator: Wantland, J L & Kidd, Jr, G J
Partner: UNT Libraries Government Documents Department
open access

Calibration of Omre Fuel-Element Surface Thermocouple Assembly

Description: Studies were made to determine the actual surface temperature of OMRE fuel elements if the thermocouple were not present. Chromel-alumel thermocouples are being attached to the fuel plate cladding of Type 304 stainless steel. These wires are in contact with the coolant stream. Heat transfer from the thermocouple junction, by conduction along the lead-wires and by forced convection to the coolant, produces a lowering of the surface temperature in the region of the junction which results in an er… more
Date: March 12, 1959
Creator: Sudar, S.
Partner: UNT Libraries Government Documents Department
open access

SECONDARY-SIDE WATER TREATMENT FOR CORROSION CONTROL IN ALUMINUM HEAT EXCHANGERS: PRACTICES AND RESULTS AT THE OAK RIDGE RESEARCH REACTOR

Description: Standard water treatment practices have proven adequate for scale and corrosion control on the secondary side of the ORR pool-cooling heat exchanger. Corrosion rates measured on specimens exposed to secondary water showed maximum corrosion rates of approximately 1 mpy during the first exposure period and these rates decreased during subsequent exposure. Examination of the heat exchanger tube bundle after 6 months and 13 months of operation showed only minor film formation and very little eviden… more
Date: August 12, 1959
Creator: Neumann, P.D.
Partner: UNT Libraries Government Documents Department
open access

EQUILIBRIUM CALCULATION IN THE SYSTEM: URANYL NITRATE, NITRIC ACID, WATER, TBP, AND KEROSENE DILUENT USING THE ORACLE DIGITAL COMPUTER

Description: A set of equations was written which allowed the calculation of equilibrium concentrations in the solvent phase of nitric acid and uranyl nitrate, given the initial TBP concentration in the solvent and the aqueous phase concentrations of acid and uranium. An ORACLE subroutine was written based on these equations which will calculate a set of equilibrium values in about 35 milliseconds. The subroutine was incorporated into a short program to calculate equilibrium points. A set of calculated poin… more
Date: August 12, 1959
Creator: Jury, S. H. & Whatley, M. E.
Partner: UNT Libraries Government Documents Department
open access

The self-concentration of high level Purex wastes in the hot semiworks waste concentrator

Description: Prior to the startup of the Purex Plant it was considered desirable to study the ``self-concentration`` of wastes likely to be encountered in the Purex waste storage system. Consequently, a 39-inch diameter 35-foot high tank was built at the Hot Semiworks. This tank was designed to represent a core of the 75-foot diameter Purex waste tanks. During the period of Purex testing at the Hot Semiworks the tank was filled with ``typical`` Purex waste and self-concentration phenomena were studied. As p… more
Date: January 12, 1959
Creator: DeWitt, R. D. & Sloat, R. J.
Partner: UNT Libraries Government Documents Department
open access

PROMPT RADIATION EFFECTS ON CABLES AND LINEAR POWER INSTRUMENTATION CHANNELS

Description: Tests were conducted to determine the amount of error introduced in reactor power data by radiation-induced voltages in cables and electrometer preamplifier chassis. The results, obtained near the central exposure facility of the KEWB (Reacter Safety Experiments), showed no observable radiation effects under the conditions of present use. Cable insulation resistance was measured during the radiation bursts. (C.J.G.)
Date: June 12, 1959
Creator: Harris, S.P. & Gardner, E.L.
Partner: UNT Libraries Government Documents Department
open access

THE BURNS UNDER A "HOT-WET" UNIFORM SPACED FROM SKIN FOR NUCLEAR WEAPON PULSES OF THERMAL RADIATION. Final Report

Description: The burns to the skin of anesthetized rats were determined for the thermal radiation pulses of a carbon arc on a hot-wet uniform when spaced 5 mm from the skin. The radiant exposures to cause burns resulting in eschar were tion pulses corresponding to 250, 1000, 2900, and 10,000 kiloton detonations, respectively. The threshold lesions were caused by volatile products not associated with ignition. The associated temperatures were recorded. (auth)
Date: May 12, 1959
Creator: de Lhery, G.P.; Derksen, W.L.; Garde, E.A.; Monahan, T.I. & Mixter, G. Jr.
Partner: UNT Libraries Government Documents Department
open access

EFFECT OF TRANSFER TIME ON THE RECRYSTALLIZATION BEHAVIOR OF BETA-COOLED URANIUM

Description: A study was made of the recrystallization behavior of beta-quenched uranium by incorporating the effects of transfer time from the beta heat-treating bath to the quench media. A critical transfer lime which relates to the time required to immerse samples at a temperature above the beta-alpha transformation in a quench media directly affects the beta-cooled structure and its ease of recrystallization upon alpha phase annealing. Within the critical transfer time, the ease of recrystallization and… more
Date: January 12, 1959
Creator: Carloni, Q. C. & Lewis, L.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen