Fecal specimens from apparently healthy dogs were inoculated into MK, DK, HeLa, and CP cells. Twenty-six cytopathic agents were isolated in MK, 11 in HeLa, and 4 in CP, but none in DK cells. Neutralization tests indicated that all but one of the viruses were either strains of ECHO type 6 or were closely related to it. Twenty-one of 29 dogs were carrying the virus.

Reactor water leaks cause outage time for locating and eliminating the leaks and for repairing damage paused by the vater that enters the reactor. The justification for equipment and process changes necessary for reducing the number of leaks and the resultant outage time is dependent on the number of leaks expected. This document presents an estimate of the future reactor water leak frequency and the average outage time charged to each leak. A water leak is defined as any entry of vater into the reactor moderator during operation. Future vater leaks are expected to result primarily from Van Stone flange failures and miscellaneous causes such as mechanical damage, fuel ruptures, and transverse cracks. It is assumed that continuous emphasis will be placed on corrosion monitoring to determine the tubes that must be replaced to prevent leaks because of internal and external corrosion. The number of water leaks is expected to average between 80 and 100 per year in the future. The normal-range of the number of leaks probably will be between 60 and 120 per year as a result of normal variation in the process tube physical condition. The number of outage hours charged per leak is expected to continue …

This report is an airphoto analysis of soil types including maps and illustrations.

A resume of nuclear physics basic to reactor operation precedes discussion of aspects of reactor physics, engineering, chemistry, metallurgy, instrumentation, control, kinetics, and safety. The object is to provide an approach to and understanding of problems in irradiation test programs in the Materials Testing and Engineering Test Reactors. (D.C.W.)

The magnetic and galvanomagnetic properties of US, including resistivity, magnetoresistance, and Hall effect, were studied. The resistivity was found to be approximately a hundred times higher in US than in the common ferromagnetic metals, but the temperature dependence of resistivity was similar, showing an abnormal decrease below the Curie point. The magnetoresistance of US was found to be negative with a sharp minimum at the Curie point. The study of the Hall effect revealed that two Hall coefficients could be identified. The extraordinary Hall coefficient, which is related to the magnetization of the material, was found to be proportional to the second power of the resistivity. The ordinary Hall coefficient R/sub o/, related to the applied field, was found to be positive and temperature dependent, with a maximum near the Curie point. The temperature dependence of R/sub o/ constituted the biggest dissimilarity between US and other ferromagnetic substances. The effective carrier concentration evaluated from this coefficient was 0.45 hole per atom at absolute zero. The study of the magnetic properties yielded values of the saturation magnetization at various temperatures which indicated that at absolute zero the atomic moment is 1.05 plus or minus 0.03 Bohr magnetons. These results are correlated …

The monthly report for the Hanford Laboratories Operation, May 1963. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics, and programming operation are discussed.

This document describes the advantages and limitations of Hanford production facilities. In addition to summarizing the technical parameters of the reactors and separations plants and their mechanical features, the unique aspects of these facilities to the production of special materials in which the Commission may be interested have been discussed. As the primary difference between the B-C-D-DR-F-H reactors and the K reactors and the K reactors is in the number and length of process channels. This report is addressed primarily to the 2000-tube reactors. K reactor characteristics are within the range of lattice and flexibility parameters described.

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From Abstract: Report discussing "the effects of developing two-phase flow regimes in a constant-pressure drop system are shown in recorded traces from a fast-response flow transducer: the mass velocity decreases and transfer-surface superheat increases with increasing steam quality."

A simple method is developed for calculating or predicting temperature distributions in spent reactor fuels in shipping casks. The method accounts for radiant heat transfer between all the individual pins in a square array. With the dimensions of the fuel bundle, the configuration factors for radiation between various tubes in the bundle can be obtained from the tabulated numerical calculations presented. The configuration factors, along with the heat generation rates, surface emissivity, and the temperature of the wall of the cask can be used to estimate the temperature distribution automatically with the computer code presented or possibly by hand calculations by the method outlined. Experimental measurements of temperature distribution in electrically heated tube arrays in steel shells that simulated shipping casks were made to test the proposed calculational procedure. Several heat generation rates and bundles containing up to 64 tubes were tested in 12-in.- and 6-in,-inner diameter shells. Tests were made with the casks in horizontal and vertical positions. The predicted temperatures were very near those observed experimentally under the conditions in which heat transfer is likely to be a problem in fuel shipment, that is, when the temperatures are near or above 200 c- C and the casks do …

Summary & Conclusions: "The study presented in this report was directed toward resolving the uncertainties in the design and prediction methods for heat transfer performance as well as toward analyzing certain aspects of the scaling problem."

The counter hodoscope experiments at incident particle momenta of 7-20 Bev/c are summarized. The data are presented, together with the associated Regge pole analyses. The effective radii, opacities, and total cross sections obtained for the interactions are included. A magnetic spectrometer setup used for low four-momentum transfer data is also described, and optical theorem predictions for pi /sup -/-p and p-p are given. (D.C.W.)

Report issued by the Brookhaven National Laboratory discussing high-pressured gamma loops. As stated in the introduction, "this latest endeavor involved three test cells, a gamma irradiation pool and supporting equipment, as well as an enlarged high-pressure gamma loop facility" (p. 1). This report includes tables, and illustrations.

A revolving drum camera--oscilloscope data display and recording system was assembled. It provides an effective photographic sensitivity an order of magnitude greater than that previously reported for utilization in time-resolved mass spectrometer analyses of rapidly occurring physical and chemical processes. A gas phase flash heating phenomenon, recorded with a Bendix TOF Mass Spectrometer operating at 20 kc, is cited as an application of the improved data recording system and as an example of timesaving data reduction procedures. (auth)

Introduction: The object of Project Agreement 22, Task 1, is to develop improved detectors which can operate up to 1000 F for in-core power monitoring. Several ideas have been developed to achieve this goal: (1) root mean square fluctuation voltage measurement of ion chamber signals, (2) thermocouple-type detectors, and (3) fabrication developments.

In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.

The ACIR Library is composed of publications that study the interactions between different levels of government. This document addresses industrial development bond financing.

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A half-plant low alum treatment test began at F Reactor on January 16, 1963. The test, which had been prompted by results obtained from a statistical analysis of fuel element ledge corrosion attack, will demonstrate whether or not high alum feed is responsible for increasing the frequency of ledge and groove corrosion attack on fuel element surfaces. The effect will be evaluated by comparing visual examination results obtained from normal production fuel irradiated in process water treated with two different alum feed rates. This report presents the results from 20 fuel charges, ten from each side of F Reactor, which were discharged such that the near side fuel pieces had been exposed for 75 days to water treated with 18 ppm alum and the far side pieces had been exposed 75 days to water treated with 8 ppm alum.

Thesis submitted to University of Tennessee, Knoxville. Activities in a program to determine the wetting behavior of pure metals such as Au, Ag, Ge, Al, and Cu on solid Be are reported. Results of similar investigations of binary alloys such as Be--Ti, Be-Zr, and Be--Pd are also included. The contact angles of the molten metals on Be as a function of temperature, exposure time, and atmosphere were measured. The solid-liquid interfacial reactions occurring as a function of test temperature and atmosphere were investigated, and the liquid- vapor and internal surface tensions for those systems in which interfacial reactions did not appear to occur were calculated. (J.R.D.)

This document details activities of the Irradiation Processing Department during the month of August, 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

Declassified 24 Sep 1973. The purpose of this work was to develop a process for recovering the uranium from spent Rover fuels. Only one reactor is used, and the process involves a 4-hr combustion of the fuel in oxygen at about 800 deg C, a 4-hr chlorination of the U/sub 3/O/sub 8/-Nb/ sub 2/O/sub 5/ ash in refluxing hexachloropropene at 180 deg C, dissolution-extraction of the UCl/sub 4/ and NbCl/sub 5/ products at room temperature by dilute nitric acid, and extraction of the uranium from the resulting acid solution with 30% TBP in Amsco diluent. The results indicate that an extract containing 50 g of uranium per liter can be produced in seven or eight extraction stages, with total uranium losses of less than 0.02%. Corrosion rates of several possible construction materials during chlorination are less than 0.1 mil/month. Problems in the process involve handling about 10% of the niobium as a solid during the liquid- liquid separations, and handling solutions containing chloride. The results of this laboratory-scale work indicate that the liquid-phase chlorination and subsequent extraction operations are reducible to large-scale practice, since these operations resemble the liquid-phase operations typically performed in radiochemical separation plants. (auth)

Declassified 24 Sep 1973. Two chloride volatility processes for the recovery of uranium from the combustion ash from spent Rover fuel were studied in the laboratory. The fuel consists of graphite impregnated with uranium carbide. The cooling channels are of niobium carbide. In each method, the uranium is isolated as UCl/sub 4/ and it may be further processed by aqueous solvent extraction (Darex) or fluoride volatility methods. The combustion-- chlorination process involves burning the fuel elements in oxygen at 700 to 9O0 deg C and then chlorinating the uranium and niobium oxide products with 15 vol% CCl/sub 4/-85 vol% Cl/sub 2/ at 500 deg C. The volatilized uranium and niobium chlorides are collected at room temperature and then separated by selective volatilization of niobium chloride by controlled heating to 400 deg C. Uranium recovery is quantitative, and less than 1% of the niobium remains with the uranium. Corrosion rates for nickel or high-nickel alloys are expected to average about 0.5 mil/month through the cycle. The combustion-chlorination process should be reducible to large-scale practice because the reactions proceed readily, and the corrosion problems are minor. In the direct chlorination process, rough-crushed Rover fuel is treated with chlorinating and mixed chlorinating-- oxidizing …