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K-Reactor Retubing Program graphite temperature study

Description: A project has been proposed and the funds allocated for the replacement of the central zone aluminum process tubes at both K Reactors with smooth bore zirconium process tubes of approximately the same outside diameter as the original tubes. Associated with this project is the problem of relieving the present graphite stack distortion in the vicinity of the process tube channels and counteracting or prereliving, at this time, the expected graphite stack distortion that, will take place over the … more
Date: December 26, 1962
Creator: Agar, J. D.
Item Type: Refine your search to only Report
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The Formation of Protons From Water by Electron Impact

Description: The relative cross section for the production of protons from water by electron bombardment was measured by a modulated crossed beam technique over an energy range from threshold to 500 ev. The appearance potential for protons was measured by comparison with the ionization potential of hydrogen and found to be 19.4 ev. This result is in agreement with earlier results. The overall curve is smooth with the exception of a slight shoulder at about 45 ev. This shoulder may indicate the presence of m… more
Date: July 26, 1962
Creator: Baker, F. S. & Brink, G. O.
Item Type: Refine your search to only Report
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Special review of selected reactor construction, operation, and program data

Description: This report documents the answers to specific questions posed by management on December 17,1962. The questions asked were: (1) What were the design and construction start and completion dates of project CG-558-600?, what was the percent power level increase design for CG-558-600?, what was the actual power level increase achieved?, what was the construction completion date of DR reactor?, what was the expansion-overbore program initiation date?, on what date was the oral overbore-type proposal … more
Date: December 26, 1962
Creator: Ballowe, J. W.; Brasfield, R. L. & Fifer, N. F.
Item Type: Refine your search to only Report
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The Scandium-Yttrium and Scandium-Zirconium System

Description: Technical report. From Abstract : "The scandium-yttrium and scandium-zirconium were studied by thermal and x-ray methods. Both systems are characterized by complete solid solubility in the low temperature hexagonal form and in the high temperature bcc form. In the Sc-Y system, there is a minimum in the solidus at 50 at. pct and 1365°C, while the solidus in the Sc-Zr system follows a nearly straight line relationship between the melting point of scandium and zirconium. There is a minimum in the … more
Date: October 26, 1962
Creator: Beaudry, B. J. & Daane, A. H.
Item Type: Refine your search to only Report
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Equation of State of Classical Systems of Charged Particles

Description: Recent developments in the classical theory of fully ionized gases and strong electrolyte solutions are reviewed, and are used to discuss the equation of state at high temperature and low densities. The pressure is calculated using the ring-integral approximation, and quantitative estimates of higher correction terms are given. The effect of short-range repulsive forces is shown by comparing the results with two kinds of potential functions: hard spheres of diameter a, and "soft" spheres for wh… more
Date: April 26, 1962
Creator: Brush, S. G.; DeWitt, H. E. & Trulio, J. G.
Item Type: Refine your search to only Report
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A Correlation for Boiling Heat Transfer to Saturated Fluids in Convective Flow

Description: An additive mechanism of micro- and macro-convective heat transfer was formulated to represent boiling heat transfer with net vapor generation to saturated, non-metallic fluids in convective flow. The final equations are [equations not transcribed]. The second equation will be recognized as the Dittus-Boelter equation with the additional factor F. The two functions F and S are defined as [equations not transcribed] where Re is the effective Reynolds number for the two-phase fluid and ΔTe is the… more
Date: December 26, 1962
Creator: Chen, John C.
Item Type: Refine your search to only Report
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Technical criteria and bases for a Zirconium-tubed K Reactor

Description: The criteria contained in this report have been established to provide the technical bases for the design modifications involved in the K-Reactor tube replacement. The ultimate intent of these criteria is to provide the basic technical data and concepts to assure: (1) technical feasibility and operability of the reactor system as modified, (2) operation of the reactor and its services to minimize nuclear and radiation hazards, and (3) appropriate lifetime of the reactor and its service faciliti… more
Date: June 26, 1962
Creator: Curtiss, D. H.
Item Type: Refine your search to only Report
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On the Structure of Sperm Whale Myoglobin. [Part] 1, The Amino Acid Composition and Terminal Groups of the Chromatographically Purified Protein

Description: The report objective is to establish the amino acid composition of sperm whale myoglobin. From Summary: "The homoprotein that comprises 96% by weight of the protein present in crystalline sperm whale myoglobin may be received into at least five components by chromatography on the carboxylic resin IRC-50."
Date: March 26, 1962
Creator: Edmundson, A. B. & Hirs, C. H. W.
Item Type: Refine your search to only Report
open access

EVALUATION OF (Th,U)C$sub 2$, CARBON-COATED (Th,U)C$sub 2$ PARTICLES, AND CARBON COATINGS

Description: Thorium and uranium carbide nuclear fuel particles were evaluated by metallographic and x-ray diffraction techniques. Techniques were developed to etch the polished surface of Th--U carbide to reveal the grain structure. In addition, techniques to determine particle density and coating thickness were developed. Comparison of the data indicates that the use of spherical particles allowed for more precise determination of the coating thickness, density, and strength of coatings. Strength of indiv… more
Date: April 26, 1962
Creator: Engle, G. B.; Luby, C. S. & Bokros, J. C.
Item Type: Refine your search to only Report
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Stress Corrosion of Type 304 Stainless Steel in Simulated Superheat Reactor Environments. [Part] 1. Informal Aec Research and Develoment Report 568-Tio-2

Description: A fuel jacket failure that occurred in May 1961 in the Type 304 stainless steel clad fuel element exposed in the Vallecitos Boiling Water Reactor superheated steam loop (SADE) was attributed to chloride stress corrosion cracking. In order to better understand the failure, a test program was carried out to try to reproduce the rapid stress corrosion attack in the simulated superheat reactor environment of the CL-1 superheat facility. The methods of corrosion testing under heat transfer condition… more
Date: February 26, 1962
Creator: Gaul, G. G.; Pearl, W. L. & Siegler, M.
Item Type: Refine your search to only Report
open access

HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 2

Description: Twelve Zircaloy-2 clad UO/sub 2/ specimens, irradiated in the NRK to about 15,500 Mwd/t and decayed about 9 months, were declad and core dissolutions completed. The pellets were fractured brt were essentially intact (i.e. had not fallen apart) when declad. The U losses ramged from 0.03 to 0.09%, due to solubility of U(IV) in the Zinflex reagent, and the U losses from 0.01 to 0.04%. The core pellets were 99.5% dlssolved in 4 M HNO/sub 3/-0.1M Al(NO/sub 3/)/sub 3/ in 5 hr, which was slightly fast… more
Date: January 26, 1962
Creator: Goode, J.H. & Baillie, M.G.
Item Type: Refine your search to only Report
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Prerequisite requirements for higher graphite temperature limits and/or nitrogen atmosphere at all reactors

Description: The graphite temperature limits specified in the process standards-are being closely approached or have limited power levels at B, D, DR, and reactors. An increase of approximately 50--100 C in graphite temperature limits at these reactors would permit year-around operation on bulk outlet temperature limits. There has been considerable recent interest in extending to all reactors the use of nitrogen as a reactor gas constituent. With present graphite temperature limits, significant benefit from… more
Date: February 26, 1962
Creator: Graves, S. M.
Item Type: Refine your search to only Report
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NBS Viscometer Calibrating Liquids and Capillary Tube Viscometers

Description: Report discussing measurements of viscosity made with relative viscometers. These instruments must be calibrated with liquids whose viscosities are known. NBS provides a series of 10 oils for this purpose. Their viscosities range from 0.02 to 450 poises and their temperature coefficients of viscosity range from 2.1 to 9.4 percent per degree C. The less viscous oils are more stable. Correction formulas for errors or conditions are presented.
Date: December 26, 1962
Creator: Hardy, R. C.
Item Type: Refine your search to only Report
open access

Design of production test IP-490-A-FP evaluation of diffusion bonded fuel elements

Description: I&E uranium cores are to be jacketed by Sylcor and Hanford utilizing the ``Solid State Diffusion-Hot Pressure Bonding`` process. Hanford will also jacket cores by the ``Solid State Diffusion`` process, by ``Gas Pressure Bonding`` and ``Hot Die Sizing``. In this process, a layer of nickel is placed between the aluminum and uranium to prevent diffusion of the aluminum into the uranium and furnish a layer of metal capable of limiting diffusion with both the aluminum and uranium. The completed fuel… more
Date: March 26, 1962
Creator: Hodgson, W. H. & Clinton, M. A.
Item Type: Refine your search to only Report
open access

The Fast Rise Pulser

Description: A circuit is described developed to fill the need for a pulser with a 15-20 volt amplitude into the 93 ohm line, stable, transistorized and low cost, fast 10 Nano second rise, and a variable repetition period from 0.5 sec. to 4 sec.
Date: June 26, 1962
Creator: Kiriokos, George
Item Type: Refine your search to only Report
open access

Transport Calculations for Proton Shielding

Description: The dose rate and integrated dose, inside a shield, due to an arbitrary proton flux was calculated. To this end, it was necessary to ascertain the effect of the shield on the incident flux. This aspect of the problem is considered. The analysis takes into account both proton ionization energy loss and secondary-particle production, using the transport method of successive generations. The secondaries considered are protons, neutrons, and pi mesons. (auth)
Date: October 26, 1962
Creator: Litton, G.; Goldstein, R. & Wallace, R.
Item Type: Refine your search to only Report
open access

Production test IP-486-D, Irradiation of corrugated fuel elements

Description: The objective of this production test is to authorize the irradiation of three natural uranium corrugated I&E-type fuel elements in a KE Reactor front-to-rear test hole. The ultimate exposure of Zircaloy-2 clad, coextruded, uranium-cored fuel elements may be limited by localized tensile necking and splitting of the jacket. The total deformation capability of a fuel element is increased by corrugating the outside surface so the perimeter is greater than that of a circle circumscribing the equiva… more
Date: January 26, 1962
Creator: Marshall, R. K. & Kratzer, W. K.
Item Type: Refine your search to only Report
open access

Centrifugal Distortion Corrections to Calculated Thermodynamic Functions

Description: Complete parition functions for non-rigid rotators are obtained for the linear, spherical top, and symmetric top cases, From these are derived expression giving the corrections to the thermodynamic functions due to centrifugal distortion as functions of the rotational distortion constants D. Numerical examples are given for HCN, methane, and ammonia.
Date: December 26, 1962
Creator: McDowell, Robin S.
Item Type: Refine your search to only Report
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