Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined include core screen samples, core specimen array No. 1, blanket specimen array No. 2, core solution line specimen arrays No. 103 and 103A, and blanket solution line specimen array No. 203. These data include corrosion rates, computed from specimen weight-changes, and results of chemical analyses of scales removed from the specimens or specimen holders. A summary is included of the HRT operating schedule during exposure of the specimens and of the status of examinations for the specimens removed from the reactor prior to run 20. (auth)

The requirements for multiple-coincidence counting systems with 10{sup -8}- to 10{sup -9}-sec time resolution can be met economically with presently available high-frequency transistors. The design of solid-state coincidence circuits, amplitude discriminators, and decade scalers is considered and their operation discussed. Several systems have been designed utilizing up to 180 channels from scintillation detectors.

The advantages of the use of organic liquids in fission reactors to minmize corrosion and pressure problems were studied relative to the solution of thorium in such fluids. Thorio-organic compounds were prepared from organic acids, diketones, and other chelating compounds. Salts of carboxylic and phospho- organic acids were insoluble. The chelate with dibenzoylmethane was soluble in molten biphenyl but was decomposed at 300 deg C. The general low solubility of thorio-organic compounds in nonpolar solvents can be explained by steric effects. The large thorium atom has the ability to form strong coordination complexes with adjacent molecules, leading to coordination polymers. The effect can be minimized by shielding the thorium nucleus with large organic groups such as dibenzoylmethane. The large, branched organic groups needed to impart solubility limit the maximum solubility. (auth)

ABS>A recording potentiometer was modified to provide a versatile instrument that can be applied to a variety of problems without time-consuming changes. Ranges may be selected in six spans, from 0.5 to 100 mv. No adjustments of amplifier gain are required when switching from one range to another. Zero suppression is continuously variable over a plus or minus 100 mv range by means of coarse and vernier controls. Cold junction compensation is provided for four standard thermocouples, and chart speeds from 1/2 to 16 im- ./ hr may be selected at will. (auth)

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This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.

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The process criteria proposed use of the existing organic wash column, 10, as a stripping column for the neptunium accumulation and isolation cycles. It is now proposed to employ a new processing concept which will permit the use of the scrub section of the neptunium extraction column, 1S, for neptunium stripping thereby obviating the use of the 10 Column. This proposed new scheme will provide increased neptunium stripping efficiency and greater processing flexibility for the 1S Column. The revision will require four new jumpers, but will permit the deletion of eight jumpers required for the original proposal. This document discusses the technical bases and incentives for the proposed change and presents revised flow diagrams and jumper routings.

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The distorted-wave theory of direct nuclear reactions is presented in a unified manner, in which the effects of assuming various reaction mechanisms and nuclear models appear only in certain radial form factors. The zero-range approximation is used, and spin-orbit coupling is neglected in the distorted waves. Formulas are given for transition amplitudes, cross sections, and polarizations. A description is given of the IBM-704 computer code SALLY that is based on these formulas. (auth)

The differential cross sections for elastic scattering of 14-Mev neutrons from nitrogen and oxygen were measured in the angular range from 17 to 140 deg , using liquid targets and annular ring geometry. Inelastic scattering to the 2.31 and 3.95-Mev levels in N/sup 14/ and to the levels near 6 and 7 Mev in O/sup 16/ was investigated over a more restricted angular range. The 2.31-Mev level in N/sup 14/ was not excited appreciably, in disagreement with previously reported results. For both elements, the elastic scattering cross sections (determined to an accuracy of 10%) were found to be appreciably higher than the optical model predictions by Rjorklund and Fernbach for scatterirg angles larger than 70 deg . The inelastic cross sections measured are, within experimental accuracy, the same as the corresponding (p,p') cross sections. (auth)

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The purpose of this document is to present the numerical results of a production test of the last ditch water backup system performed at B and C reactors on December 15, 1961. The main purpose of the production test was to determine more accurately the capacity of the export system for supplying flow to a dual reactor area under several simulated emergency conditions where BPA power to all areas has been interrupted and the steam supply to one old area has been lost. In addition, the flow capacity of the high tanks to,the reactor was tested alone and in parallel with the export system, and the action of the surge suppressors at all areas was recorded when cycling of the surge suppressors was deliberately induced.

BS> The potential advantages of neutron radiography as an inspection method are discussed along with a historical review and discussions of neutron sources and detectors. The results of the current investigation of neutron-image detectors are discussed in regard to photographic speed, relative neutron-gamma response, and resolution comparisons. Two neutron-image detecting methods are discussed. In one, the direct-exposure method, both the converter screens and the film are exposed to the neutron beam together. The other method, the transfer method, makes use of a radioactive, image-carrying screen, which is transferred to photographic film after the neutron exposure is completed. The direct-exposure method results in increased speed, but has the disadvantages that the film also responds to any gamma radiation in the imaging beam and that, in most cases, improved image resolution can be obtained with the transfer method. Reference is given to several application possibilities. (auth)

The initial 30-Mw SRE Core III loading will contain a total of 33 fuel elements. Of these, the central 7 fuel elements are test elements and the remaining 26 are driver elements; 4 of the 7 test elements are designated as standard test elements. These elements are identical to the driver elements with the exception of the active fuel length. The remaining 3 test elements are designated as special test elements and incorporate fuel rods of smaller diameter and increased enrichment to obtain higher burnup rates, greater specific power, and higher fuel temperatures. Geometry design data for the various elements considered in the analysis was obtained from Dwg. No. 650 deg F, the mixed-mean coolant outlet temperature for the core at 1200 deg F ( plus or minus 15 deg F), the maximum average temperature on the cladding at 1275 deg F, and the maximum fuel temperature in the range of 2000 to 2100 deg F. The thermal performance of the fuel elements was analyzed with the SORTD code and the Heating code. The results of the analysis are presented in tabular form. Axial temperature profiles are also presented for representative fuel elements. The core outlet coolant mixed-mean temperature was …

Selected components from a staianless steel nonregenerative heat exchanger removed from the U.S.S. Nautilus (SSN571) have been examined for evidence of stress-corrosion cracking. The examination was conducted on three baffle plates, all primary-face seal welds, and the tubes and the surrounding tube sheets of 7 out of a total of 35 tubes. Maximum operating temperature of the heat exchanger was 260 ction prod- F for the inlet primary water and 164 ction prod- F for the exit secondary water. Chloride content of the secondary water averaged 5 ppm, with a maximum of 15 ppm. Only one suspected stress-corrosion crack was found in the components normally in contact with the secondary water. The crack, 2.5 mils in depth, was located on a fully exposed tube. At the 95 per cent confidence level this represented a probability of finding cracking on fully exposed surfaces in 0 to 60 per cent of the rest of the tubes in the heat exchanger. Severe stress-corrosion cracking was found in tubes in the tube-sheet drain area at the juncture with the inner tube sheet at the inlet end, where secondary water seeped past the expanded tubes. Cracks were detected in five of seven tubes for a …

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In coolant system such as NPR's, the coolant activity level increase with each succeeding pass through the reactor flux until a saturation limit is reached. Therefore, the activity level of the NPR coolant system will be much higher than that of the old reactor once-through systems. This report is the determination of the specific activities (disintegrations/cc{center dot}sec) of the various coolant impurities which determine the total activity of the coolant system. 10 refs., 13 figs., 2 tabs.

The outgassing characteristics of specimens of the EGCR moderator graphite stock were determined in vacuo to a maximum temperature of 1000 deg C using external resistance heating and to 1800 deg C by induction heating. The specimens examined were cut from several locations in two of the 18-in. x 18-in. x 20-ft graphite bars which had been prepared under fabrication conditions comparable to those used for the graphite columns present in the Experimental Gas- Cooled Reactor. Data are given which show the effect of the position of sampling of the bars on the density of the graphite. The volume and composition of desorbates obtained at 300, 600, and 1000 deg C as a function of specimen size and position of specimen within the bars also are given. The volume-time relationships at 300 and 600 deg C can be expressed satisfactorily by v = A log t + B over extended intervals of time. A linear relationship prevails at 1000 deg C only after heating for longer than approximates 800 min. The volume and composition of the desorbates obtained at 1000, 1400, and 1800 deg C using induction heating are tabulated. (auth)