137 Matching Results

Search Results

Results: 1 - 24 next
open access

Storm Data and Unusual Weather Phenomena, Volume 6, Number 7, July 1964

Description: Monthly report containing a chronological listing, by state, of hurricanes, tornadoes, thunderstorms, hail, floods, drought conditions, lightning, high winds, snow, temperature extremes and other weather phenomena. It also provides information on storm paths, deaths, injuries, and property damage.
Date: August 31, 1964
Creator: United States. Weather Bureau.
Partner: UNT Libraries Government Documents Department
open access

Effect of 1200ºF Sodium on Austenitic and Ferritic Steels Progress Report: July 1964

Description: This is the forty-seventh progress report from July 1964 detailing progress made in areas such as progress made on creep, creep-rupture, and fatigue tests for Test 3 and initiation of these tests for Test 5.
Date: August 14, 1964
Creator: Andrews, R. C.; Barker, K. R. & Werner, R. C.
Partner: UNT Libraries Government Documents Department
open access

Analysis of the Combustion of Graphite-Uranium Fuels in a Fixed Bed or Moving Bed

Description: The first step in a proposed processing method for recovery of uranium from graphite-uranium fuels consists of oxidation of the fuel by oxygen to volatilize the carbon. Residue ash from the combustion step can be treated in a variety of ways to recover and purify the uranium. The combustion step may be caried out by contacting the solid fuel in a fixed or moving bed with a stream of oxygen-bearing gas in a tubular or annular reactor. Oxidizing gas may be introduced to the reactor at several poi… more
Date: August 13, 1964
Creator: Scott, Charles D.
Partner: UNT Libraries Government Documents Department
open access

Graduate Programs for the Health Physicist in the United States

Description: The first man-made nuclear reactor -- or "pile" as it was then called -- was rather hurriedly improvised and operated in a crowded space under the athletic bleachers of Stagg Field at the University of Chicago on December 2, 1942. Just prior to this time, there began the assembly of a group of physicists with an unusual assignment. They were determined that radiation hazards of unprecedented proportions must be coped with successfully in the conduct of reactor programs as planned. Since these p… more
Date: August 13, 1964
Creator: Morgan, K. Z. (Karl Ziegler), 1908-
Partner: UNT Libraries Government Documents Department
open access

Thermal Properties of Grade CGB Graphite

Description: Grade CGB graphite is a nuclear graphite which is basically an extruded petroleum coke bonded with coal tar pitch. No carbon blacks are used and the low-permeation graphite is finished through a series of impregnations and heat treatments with a final heat treatment of all components to 2800 degrees C. A listing of the results obtained is given in Table 1. The results at 51 degrees C are considered questionable. There was a slight contamination of the 90% Pt 10% Rh-Pt thermocouples at 910 degre… more
Date: August 11, 1964
Creator: Moore, J. P. & Godfrey, T. G.
Partner: UNT Libraries Government Documents Department
open access

Comparison of the Thermal Conductivity, Electrical Resistivity, and Seebeck Coefficient of a Hight-Purity Iron and Armco Iron to 1000 [degrees] C

Description: The thermophysical properties of Armco iron such as thermal conductivity, electrical resistivity, and Seebeck coefficient have been extensively investigated and reviewed up to 1000 degrees C. Few investigations of such properties have been made on high purity iron. If such a study is made using the same apparatus to determine the properties of two purity levels of iron, then several significant intercomparisons can be made which add meaning to data on a single material. The systemic errors for … more
Date: August 11, 1964
Creator: Moore, J. P.; Fulkerson, W. & McElroy, D. L.
Partner: UNT Libraries Government Documents Department
open access

A Thermal Comparator Apparatus for Thermal Conductivity Measurements from 50 to 400 [degrees] C

Description: The experimental details, mathematical models, and typical data for a rapid comparative method for thermal conductivity measurements are presented. The method consists of measuring the temperature change of a small silver sphere after it is brought in contact with a small disk-shaped specimen which was initially at ta higher temperature. This temperature change was calibrated in the range of 50 to 400 degrees C by making measurements on samples of know thermal conductivity. The accuracy of this… more
Date: August 11, 1964
Creator: Kollie, T. G.; McElroy, D. L.; Graves, R. S. & Fulkerson, W.
Partner: UNT Libraries Government Documents Department
open access

Deposition of Submicron-Size Particles in Ventilation Ducts

Description: The purpose of this study was to investigate mathematically the concentration decrease due to particle deposition phenomena in highly concentrated monodispersed aerosols (mean particle size less than 1.0 mu) flowing through ventilation ducts. It was found that, from the standpoint of removal, the decrease in concentration due to deposition on duct walls was insignificant; but, when considering contamination on duct walls, the amount deposited, even though small when compared with the amount in … more
Date: August 1964
Creator: Davis, L. P.
Partner: UNT Libraries Government Documents Department
open access

IPD production projections

Description: This document reports the IPD production projections and reactor inventories for Hanford C and K reactors. Tables included contains the following information: Operating efficiency, exposure, conversion ratio, tonnage, production, and power level.
Date: August 4, 1964
Creator: Lang, L. W.
Partner: UNT Libraries Government Documents Department
open access

Through-reactor flow calculated from high tank-high velocity flush data

Description: To satisfy reactor coolant supply criteria requires a knowledge of available emergency flow rates from secondary and last-ditch systems. This document presents a method for calculating high-tank flow contribution to the last-ditch coolant system from routine high tank-high velocity flush data. The measured flush flow is converted to equivalent through-reactor flow at 20 C and at the critical time of high-tank takeover from flywheel decay.
Date: August 20, 1964
Creator: Morrissey, J. E.
Partner: UNT Libraries Government Documents Department
open access

Production test IP-696 evaluation of arch-rail supports

Description: Large scale self-support fuel usage at the K Reactors began in mid-1963. With the advent of the new fuel element concept, self-support development work in different areas was required. One such area was that of the supports, or rails, used on the elements. The initial self-support rail design on the elements, in order to meet production commitments, was only slightly modified from previous test models. These rails were identified as ``bridge rails.`` Development of the self-supports has continu… more
Date: August 7, 1964
Creator: Hladek, K. L.
Partner: UNT Libraries Government Documents Department
open access

Hanford Laboratories monthly activities report, July 1964

Description: This is the monthly report for the Hanford Laboratories Operation, July 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.
Date: August 14, 1964
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Department Monthly Report: July 1964

Description: This report, for July 1964 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.
Date: August 21, 1964
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
open access

Reactor phase-out discharge planning

Description: Reactor phase-out discharge planning involves forcing all tubes into a discharge pattern such that they can all be discharged at the appointed time with maximum fuel utilization. When considering reactors operating on the block discharge concept, action must be taken early to cause the fringe to reach goal exposure at the same times as the central core. For the case of alternate row or random discharge of core material, there is the additional problem of discharging all core tubes at a single o… more
Date: August 6, 1964
Creator: Dunn, R. E.
Partner: UNT Libraries Government Documents Department
open access

Physics aspects of removal of overbore test facility

Description: Investigation of several alternative methods of modifying the C- Reactor overbore test facility in order to terminate the production tests has been completed. The results are presented in this report.
Date: August 10, 1964
Creator: Bailey, G. F.
Partner: UNT Libraries Government Documents Department
open access

Modified tubular support patterns: Ribbed and ribless process tubes

Description: Reactor support charge designs and patterns have been numerous and varied over the past few years, the basis for acceptance of a particular support loading being determined from a consideration of fabrication costs and the hydraulic characteristics of the proposed dummy load as it applies to a particular reactor. Since the first three or four dummy pieces downstream of the fuel column (and upstream of the column in a spline tube) are discarded after the irradiation process, it is desirable to u… more
Date: August 25, 1964
Creator: Angle, C. W.
Partner: UNT Libraries Government Documents Department
open access

Irradiated Fuel Age Determination Study

Description: The release of uncontrollable quantities of harmful fission products such as I{sub 131} upon processing areas. At present this is done by procedural techniques using cards, filing techniques, and cross checks. These methods are entirely independent of the characteristics of the fuel itself and are subject to failure from human error. It is therefore advantageous to find a method of determining the age of irradiated fuel after discharge from the properties of the fuel. Such a method, with its re… more
Date: August 31, 1964
Creator: Cooley, D. E.
Partner: UNT Libraries Government Documents Department
open access

K reactor mixer study aluminum spline tubes

Description: Reference 1 gave mixer recommendations for aluminum spline tubes at the K reactors. On completion of the study, R. F. Corlett requested a more detailed economic study of mixer useage at KW reactor. R. G. Clough also requested additional information on use of mixer elements in fringe tubes. In order to answer these requests, additional information was needed and requested. A. W. Medcalf replied giving enriched metal requirements in support of mixers. No other information vas received so it was n… more
Date: August 18, 1964
Creator: Hough, C. G.
Partner: UNT Libraries Government Documents Department
open access

Production Test IP-708, Oil-quenched hot-die-sized element evaluation

Description: The objective of this test is to evaluate the effects of oil quenching, alpha annealing, and an Al-Si braze pre-canning treatment on the irradiation behavior of hot-die-sized fuel elements.
Date: August 24, 1964
Creator: Hladek, K. L.
Partner: UNT Libraries Government Documents Department
open access

KER-2 operating report: Test K-2-22

Description: The purpose of this test was to evaluate the behavior of natural lithium-bearing materials and to provide samples for production and extraction information. Testing of the target elements was done in conjunction with a test evaluating the behavior of NIEl fuel elements. Conditions for operation during the test were similar to, or more severe, than conditions expected in N Reactor.
Date: August 3, 1964
Creator: Christensen, G. P.
Partner: UNT Libraries Government Documents Department
open access

Production test IP-694-A: Depleted uranium irradiation, K reactors

Description: The AEC has indicated a need for plutonium with a high concentration of the Pu-240 isotope. Concentrations up to 25 W/o Pu-240 have been requested with a firm commitment given for 25 kilograms of plutonium with at least 18 W/o Pu-240. To meet this production demand, irradiation of depleted uranium, 0.22 W/o U-235, will be undertaken. This test authorizes half of the irradiation in a Hanford K reactor, outlines the general plans, and presents the details of the irradiation. The objective of this… more
Date: August 17, 1964
Creator: Gross, P. D. & Hladek, K. L.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen