Search Results

open access

Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents

Description: The ORNL analog computer was used to examine one aspect of a safety system for the EGCR. The thermal behavior of the fuel as a result of increases in reactivity at various power levels and gas flows was examined. Safety actions initiated by wither a flux-minus-flow signal or a reactor outlet gas temperature signal were included in simulation.
Date: December 16, 1960
Creator: Pierce, R. M.
open access

Report of the Forty-Fifth National Conference on Weights and Measures, 1960

Description: Report of the annual conference on weights and measures, hosted by the U.S. National Bureau of Standards in Washington D.C. It includes conference proceedings, a list of attendees, information about committees and officers, and other reports or commentaries discussed at the meetings.
Date: December 16, 1960
Creator: United States. National Bureau of Standards.
open access

Preliminary Design Criteria for the Interim Storage of High-Level Radioactive Liquid Wastes

Description: Approximately five years of process improvements, and production line waste handling experience have been accumulated since the newest tank farm, 241-A, was placed into operation. Process improvements and modifications have resulted in waste volume reductions by decreasing the quantity of solids remaining in the liquid wastes from a unit of production. The resulting concentration of fission products has produced mildly boiling solutions in the storage containers permitting further waste volume … more
Date: December 16, 1960
Creator: Stivers, H. W.
open access

EUROCHEMIC ASSISTANCE PROGRAM: COMMENTS BY ICPP, DATED FEBRUARY 25, 1959, ON QUESTIONS LISTED IN ORNL-CF-59-1-75

Description: The handiing of interface j-ettings in waste solution processing and determination of mono-, di-, and tri-butyl phosphates in process solvents are discussed. Decontamination procedures used in ICPP are outlined. Evaporator deentrainment at ICPP is discussed. Information on Lapp pulse units and on continuous dissolution is presented. (D.L.C.)
Date: November 16, 1960
Creator: Weech, M.E.
open access

n+-p ELASTIC SCATTERING AT 310 Mev: REC0IL-NUCLEONPOLARIZATION

Description: The recoil-proton polarization in {pi}{sup +}-p elastic scattering at 310-Mev incident-pion laboratory kinetic energy has been experimentally measured at four scattering angles with scintillation counters. Polarization values obtained, related rms experimental errors, and mean center-of-mass recoil angles are: +0.044 {+-} 0.062 at 114.2 deg. =0.164 {+-} 0.057 at 124.5 deg, -0.155 {+-} 0.044 at 133.8 deg, and -0.162 {+-} 0.037 at 145.2 deg. The sign of the polarization is defined to be positive … more
Date: November 16, 1960
Creator: Foote, James H.; Chamberlain, Owen; Rogers, Ernest H.; Steiner,Herbert M.; Wiegand, Clyde E. & Ypsilantis, Thomas.
open access

π<sup>+</sup>-p ELASTIC SCATTERING AT 310 Mev: PHASE-SHIFT ANALYSIS

Description: A comprehensive phase-shift analysis of {pi}{sup +}-p elastic-scattering data at 310-Mev incident-pion laboratory kinetic energy has been performed. The experimental data utilized include measurements of the differential and total cross sections and of the recoil-proton polarization. The D-wave phase shifts were found to be definitely needed in order to attain an adequate fit to the data. A general search for phase-shift solutions was carried out, using S-, P-, and D-wave phase shifts. One solu… more
Date: November 16, 1960
Creator: Foote, James H.; Chamberlain, Owen; Rogers, Ernest H. & Steiner, Herbert M.
open access

Examination of Components for Crud and Corrosion 1-B Heat Exchanger Handhole Area. Core I, Seed 1. Test Results T-612080

Description: The extent and location of corrosion, crud deposits, and defects in the ends of the 1-B heat exchanger after removing the handhole covers were determined. There was no visual evidence of pitting or corrosion inside the ends of the heat exchanger. A radiochemical analysis of a smear sample taken from the inside of number one handhole showed the presence of the following isotopes- Fe/sup 59/, Co/ sup 58/, s1>s, and Zr/sup 95/. A radiation survey performed in four handholes indicated a maximum lev… more
Date: October 16, 1960
open access

A Compilation of Room Temperature and 1200 F Properties of Metallic Materials With Specific Reference to Their Use as Fuel Cladding in Sodium Cooled Thermal Reactors

Description: A compilation is presented of room temperature and 1200/sup o/F properties of a large number of alloys which might be considered for use in a sodium-cooled reactor. Specific consideration is given to the use of such materials as fuel cladding. The arbitrary basis for property comparison is type 304 stainless steel. The study was made of 10 classes of alloys. These alloys are alloy steels, ferritic stainless steels, austenitic stainless steels, iron and iron-aluminum alloys, precipitation-harden… more
Date: August 16, 1960
Creator: Kline, H.E.
open access

FISSION-GAS-RELEASE FROM UO$sub 2$, INTERIM REPORT NO. 1

Description: The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of primary interest to the Gas-cooled Reactor Project. Fuel tests consisting of UO/sub 2/ pellets encapsulated in Inconel or stainless steel were irradiated in the LITR, ORR, and ETR. The capsules were pierced in hot cells, and the gases collected in evacuated systems. Fractions of this gas, of suitable activity for counting, were taken and then analyzed by gamma spectrometry. Larger fractions of gas wer… more
Date: August 16, 1960
Creator: Morgan, J. G.; Morgan, M. T. & Osborne, M. F.
open access

PROGRESS REPORT ON FUEL ELEMENT DEVELOPMENT AND ASSOCIATED PROJECTS

Description: ; 9 < 4 6 9 7 ; 6 8 7 6 sting Deactor (MTR) has sought to develop improved, economical, long-life fuel assemblies through a comprehensive study of various fuel compositions, enrichments, claddings, burnable poisons, fuel and poison distributions, and fuelelement geometry optimization. The core materials, including uranium -- aluminum alloys, uranium oxide -aluminum cermets, thorium, thorium oxide, boron, gadolinium, dysprosium, and iridium, are tested in pilot-plant scale by irradiating them as… more
Date: August 16, 1960
Creator: Francis, W.C. & Craig, S.E. ed.
open access

Use of Isolated Junction Sheathed Thermocouples for Moderator Temperature Measurements

Description: Two types of enclosed hot junction arrangements are possible with sheathed mineral insulated thermocouples. They are the integral junction and he isolated junction. The integral junction is formed by welding, soldering, brazing or forging the two wires into the end of the sheath. The process forms a good thermal and electrical contact between the three materials.
Date: June 16, 1960
Creator: Lovett, D. B.
open access

Flow Properties of Superfluid Systems of Fermions

Description: The nonspherically symmetric solutions to the Bardeen-Cooper-Schrieffer theory are given a physical interpretation in terms of an anisotropic fluid model. These solutions have been used previously to predict a phase transition in liquid by He{sup 3} by Emery and Sessler and Anderson, Morel, Brueckner, and Soda. An investigation of the flow properties of such systems is made that involves the calculation of the effective mass for flow in a straight channel and the moment of inertia of a cylindri… more
Date: May 16, 1960
Creator: Glassgold, A. E. & Sessler, A. M.
open access

Illumination of 80$sub 4$ Chamber

Description: The needed illumination intensity is estimated from the 20-in. and 72- in. chambers to be 50 and 160 lumen-sec/ft/sup 2/ respectively. Possible source distributions are considered. With in intensity of 100 lumen-sec/ft/sup 2/ and a source brightness of 100 lumen-sec/ster. cm/sup 2/, the aperture is calculated to have a diameter of 8.6 cm. (D.L.C.)
Date: May 16, 1960
Creator: Kraybill, H. L.
open access

The ML-1 Design Report

Description: From abstract: "This report describes the design of the mobile nuclear power plant which is to be the prototype of a mobile, low-powered nuclear power plant intended to furnish electrical power in remote locations."
Date: May 16, 1960
Creator: Linenberger, G. A.
open access

A Proposal for Criticality Control Measurements Using Pulsed Neutron Methods

Description: Consideration is given to the possibility that in certain types of processing or storage facilities handling enriched fissionable isotopes the pulsed neutron method can give a useful measure of the subcriticality of the system. The proposed method describes how the concentration and multiplication constant are determined for an assembly of unknown concentrations. Such measurements might be undertaken if high levels indicate the possibility of excessive concentrations of fissionable materials. E… more
Date: May 16, 1960
Creator: Silver, E. G.
open access

THE REACTION RATE OF SODIUM SULFITE WITH DISSOLVED OXYGEN. Technical Report No. 73

Description: The reaction rate of sodium sulfite was studied as a function of oxygen concentration, Na/sub 2/SO/sub 3//O/sub 2/ ratio, temperature, catalyst, pH and surface/volume ratio.The reaction rate of hydrazine with dissolved oxygen was also studied. Oxygen removal is incomplete when the sulfite to oxygen ratio is leas than the stoichiometric quantity. With the stoichiometric quantities of oxygen and sodium sulfite present, removal is incomplete at 100 deg F in 1 min, at 200 deg F, about 95% of the ox… more
Date: May 16, 1960
Creator: Rodgers, S.J.
Back to Top of Screen