923 Matching Results

Search Results

Results: 1 - 24 next
open access

Gas purification facilities at Purex: Process study

Description: This report provides a summary of the results of a process study, requested by the Atomic Energy Commission an the recovery of krypton and xenon from irradiated uranium at the Hanford Purex Plant. This request was prompted by original Commission forecasts of the expanded requirements for Krypton-85 for commercial phosphorescent signal lights and markers and for xenon isotopes of low neutron cross-section for use in liquid xenon scintillation counters, in connection with D.M.A., government and u… more
Date: December 31, 1958
Creator: Michels, L. R. & Gerhart, J. M.
Partner: UNT Libraries Government Documents Department
open access

PRELIMINARY REPORT ON HEAT GENERATION AND STRESSES IN THE WALL OF A SPHERICAL HRE-4 PRESSURE VESSEL

Description: The heat geueration and thermal stresses in spherical HRE-4 vessels 3 to 4 1/2 ft in diameter with clad and solid stainless steel walls were invegtigated. Parameters included thorium slurry concentrations and moderator material (D/sub 2/ O and H/sub 2/O). The prirnary purpose of this study was to determine the influence of thermal stresses on the selection of the core size for the HRE4 reactor. Curves are presented which facilitate relatively rapid determination of stresses for the range of ves… more
Date: December 31, 1958
Creator: Cheverton, R.D.
Partner: UNT Libraries Government Documents Department
open access

Reactor calculations for 105-D

Description: This report provides raw data reactor calculations for the time period of September 12, 1958 through July 21, 1960.
Date: December 31, 1958
Creator: Vaughn, A. D.
Partner: UNT Libraries Government Documents Department
open access

SDR Project Quarterly Technical Progress Report No. 6 for the Period August 1, 1958 Through October 31, 1958

Description: A family of 200-Mw(e) SDR's was designed which could be operable ln 1965. They give total energy costs in the range 10 to 12 mills/kwh. The most promising of these reactors has the following characteristics: single-region design, moderate steam conditlons, natural uranium fuel, Zircaloy cladding, and stainless steel fuel tubes. A study of the applicability of SDR's to a broad range of power outputs (10 to 500 Mw(e)) was made. Although it appears reasonable to design a natural-uranium SDR with a… more
Date: December 31, 1958
Partner: UNT Libraries Government Documents Department
open access

STABILITY TESTS ON THE TYPES IN430A AND IN430B AVALANCHE DIODE REGULATORS

Description: The manufacturers' specifications for temperature coefficient of voltage and internaI impedance of the compensated avalanche diode types IN430A and IN430B appear quite promising. These devices couId be used as shunt regulators in high stability power supplies if the noise and drift rate were sufficiently small. One investigator reported the voltage did not drift more than the J-57 engin 0.002 per cent over a 7,000 hour period. Stability tests were performed on two diode samples under resonable … more
Date: December 31, 1958
Creator: Blankenship, J.L.
Partner: UNT Libraries Government Documents Department
open access

United States Atomic Energy Commission Assistance Program to the Eurochemic Company, Mol, Belgium

Description: The United States Atomic Energy Commission program of assistance to the European Company for the Chemical Processing of Irradiated Fuels ("Eurochemic"), Mol, Belgium, is presented. Included are: background, formation, purpose, and structure of the Company; basic design considerations and a brief description of the proposed plant; present status of the and a list of participating organizations and members. (auth)
Date: December 31, 1958
Creator: Shank, E. M.
Partner: UNT Libraries Government Documents Department
open access

100-N temporary construction line considerations

Description: Present thinking and planning appears to be developing from the following factors as concern the 13.8 KV temporary construction power limit. 1. It is understood that the present intent is to supply 100-N operating requirements from a single stub source in the 230 KV loop. 2. The original thoughts were to obtain construction power over a 13.8 KV line from 151-D substation. 3. Construction load requirements are now less than originally planned since steam has been substituted for electrical drive… more
Date: December 30, 1958
Creator: Mollerus, F. J.
Partner: UNT Libraries Government Documents Department
open access

MATERIAL SPECIFICATIONS FOR APPR-1 CORE II CONTROL ROD FUEL ELEMENTS AND ABSORBER SECTIONS

Description: The control rod fuel elements consist of 16 flat composite fuel plates joined to a pair of side plates to form an integral assembly with a nominal water gap spacing of 0.133 inches between fueL plates. The core section of the fuel plate contains an active fuel section and a flux suppressor section. The fuel section is composed of UO/sub 2/, B/sub 4/C, and type 304LB stainless steel. The suppressor section is composed of Eu/sub 2/O/sub 3/ and elemental stainless steel powder. The absorber sectio… more
Date: December 30, 1958
Creator: Edgar, E.C. & Robertson, R.D.
Partner: UNT Libraries Government Documents Department
open access

POWER RESPONSE FOLLOWING REACTIVITY ADDITIONS IN HRT

Description: Calculations have been performed relating the magnitude of an HRT power excursion to an instantaneous addition of reactivity (up to 1% DELTA k/sub e/). Five delayed neutron groups as well as separate heat balances over the core and blanket were accounted for in the calculation. (auth)
Date: December 30, 1958
Creator: Jaye, S. & Lietzke, M.P.
Partner: UNT Libraries Government Documents Department
open access

A PRELIMINARY INVESTIGATION OF A CHROMATOGRAPHIC COLUMN SEPARATION OF RARE EARTHS USING Di(2-ETHYLHEXYL)PHOSPHORIC ACID

Description: A new chromatographic separation of small amounts of rare earths was devised and tested with carrier-free radiotracers of Nd/sup 147/, Pm/sup 147/, and Eu/sup 155/. The method uses di(2-ethylhexyl)orthophosphoric acid (HDEHP) as a stationary phase supported on a column of aluminum oxide. and elution is with dilute aqueous hydrochloric acid. Column behavior is similar to solvent extraction using HDEHP where separation factors average 2.5 for adjacent rare earths. (auth)
Date: December 30, 1958
Creator: Winchester, J.W.
Partner: UNT Libraries Government Documents Department
open access

Further Studies With the GCRE Critical Assembly

Description: Further engineering and physics data to aid in constructing GCRE-1 were obtained in critical-assembly studies. Four major experiments were performed to investigate the effect on reactivity caused by changes in axial reflector materials, the effect on reactivity and the power perturbation caused by fast safety control-blade guides, the effect of changes in fuel-element material composition, and the effect of changes in fuel-element spacing designed to produce uniform radial power-generation rate… more
Date: December 29, 1958
Creator: Dingee, David A.; Ballowe, William C.; Egen, Richard A.; Jankowski, Francis J. & Chastain, Joel W., Jr.
Partner: UNT Libraries Government Documents Department
open access

Inspection and Maintenance Experience With Hre-2

Description: Experience in replacement of highly radioactive components of Homogeneous Reactor Experiment No. 2 is discussed, with particular emphasis on containment of air-bonne contamination and control of personnel exposure. The design and operation of tools and viewing devices developed to observe the hole in the HRE-2 core tank are described. (auth)
Date: December 26, 1958
Creator: Culver, J. S.; Shepherd, D. M. & Collins, C. W.
Partner: UNT Libraries Government Documents Department
open access

Measurements of Mechanical Properties of Pure and Uranium-Loaded Graphites at Elevated Temperatures. Final Report for June 27, 1957 Through December 15, 1958

Description: Various mechanical-property measurements on several grades of manufactured (polycrystalline) graphite stock include tensile-strength determinatftons at temperatures from 20 to 2400 deg C (plus a few at 2500 deg C), tensile stress-strain and creep tests in the range 2000 to 2400 deg C, torsional strength and stress-strain measurements from 20 to 2600 deg C, torsional creep and stress-relaxation tests in the range from 2000 to 2500 deg C, dynamic Young's- modulus determinations from 20 to 2450 de… more
Date: December 23, 1958
Creator: Green, L., Jr.; Stehsel, M.L. & Waller, C.E.
Partner: UNT Libraries Government Documents Department
open access

MILLIMICROSECOND DISCRIMINATOR

Description: A discriminator circuit for use with millimicrosecond counting equipment is described. The main characteristics of this unit are its good response to pulses as short as 3 millimicroscconds and the fast recovery time which is less than 0.15 microsec. (auth)
Date: December 23, 1958
Creator: Swift, D.F. & Perez-Mondez, V.
Partner: UNT Libraries Government Documents Department
open access

Emergency cooling and air filtration systems for HAPO reactors

Description: This report represents a critical review of existing reactor cooling systems and discusses suggested supplementary-cooling system which might be employed in emergencies resulting from such natural hazards as earthquake, equipment failure, or personnel error. In addition the subject of building filtration is discussed. Maintenance of an uninterrupted flow of cooling water is of major concern to the safety of any HAPO reactor. For some time supplementary cooling systems which would be capable of … more
Date: December 22, 1958
Creator: Adams, O. E. Jr.
Partner: UNT Libraries Government Documents Department
open access

Full reactor-E-N-load-review of the hazards from a chemical viewpoint

Description: chemical Research and Development Operation was contacted by R. Nilson of Irradiation Processing Department in order to obtain an analysis from a chemical viewpoint of the worst credible accident to a full E-N reactor loading. This analysis would be used to present to the ACRS directly or would be abstracted to prepare a supplementary report. The primary purpose of this report is to present an analysis of the chemical behavior of an E-N loading in the event of the sudden loss of coolant to the … more
Date: December 22, 1958
Creator: DeHollander, W. R.
Partner: UNT Libraries Government Documents Department
open access

K-Reactor water plant analysis

Description: The reliability of the K-Reactor water plants has been reviewed by Research and Engineering personnel; this study augments a brief analysis of the KW generator failures incident given in my letter of October 6, 1958. Our attention has been directed largely to ascertaining the requirements of the system, the consequences of possible component failures, giving general assessment of the primary features upon which reliability depends and identifying potential improvements which would increase reli… more
Date: December 22, 1958
Creator: Dickeman, R. L.
Partner: UNT Libraries Government Documents Department
open access

Model 1C shield design

Description: No Description Available.
Date: December 22, 1958
Creator: Henry, A. H.
Partner: UNT Libraries Government Documents Department
open access

DESIGN AND PERFORMANCE OF INDUCTION PUMP FOR SRE MODERATOR SYSTEM

Description: A three-phase linear induction pump was designed, constructed, and installed in the Sodium Reactor Experiment to control moderator temperature. A maximum flow rate of 91 gpm was obtained at 760 deg F, at 12.4 psi, and an efficiency of 1.7%. (C.J.G.)
Date: December 20, 1958
Creator: Baker, R.S.
Partner: UNT Libraries Government Documents Department
open access

Monthly Progress Report for the Period November 1 to 30, 1958

Description: Work directed toward developing a stainless steel clad UO/sub 2/ fuel element is reported. Methods are being developed for utilizing chemical poisoning for reactor in the reference environment. The design and development of mechanical features of fuel assemblies, control rods, baffles, the support structure, the reactor vessel closure, and fuel handling tools are presented. (For preceding period see YAEC-101.) (W.L.H.)
Date: December 20, 1958
Creator: Garbe, R. W. & Walchli, H. E.
Partner: UNT Libraries Government Documents Department
open access

Chemical Technology Division Unit Operations Section Monthly Progress Report, October 1958

Description: Tungsten and graphite are unsuitable materials of construction for a UF/ sub 6/ inlet nozzle in a continuous DRUHM reactor. Preparation of feed was completed for an extended Fluorox test. Difficulties were experienced in the operation of a fluidized bed TbNT denitrator. Flame denitration of UNH and TbNO produced mixed oxides of 1 to 14 micron mean particle size. The chloride capacity of Dowex 21K was measured, and equilibria measurements of uranium sorption from sulfate solutions were continued… more
Date: December 19, 1958
Creator: Bresee, J. C.; Haas, P. A.; Watson, C. D. & Whatley, M. E.
Partner: UNT Libraries Government Documents Department
open access

EXAMINATION OF Zr AND Ti RECOMBINER LOOP SPECIMENS

Description: Cold-worked specimens of iodide zirconium, Zircaloy-2, iodide titanium, and A-55 titanium were tested in a high-pressure recombiner loop in an attempt to duplicate anomalous results obtained in a prior recombiner loop. Hydrogen analyses and metallographic examinations were made on all specimens. The titanium materials and Zircaloy-2 picked up major amounts of hydrogen in the cell section. None of the materials tested showed appreciable hydrogen absorption in the recombiner section. Complete rec… more
Date: December 19, 1958
Creator: Rittenhouse, P.L.
Partner: UNT Libraries Government Documents Department
open access

IBM 650 COMPUTER--PROGRAM NUMBER 655 COLLATION OF ROC CODE OUTPUT

Description: Using the output of programs 653 and 654, each card of which contains the dose information for one dose point at one energy, program 655 produces the sum of the dose values of all energies for one dose point. Program details are given including 650 input and output formats, operating instructions, and guides. (auth)
Date: December 19, 1958
Creator: Stueck, C.J.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen