WorldCat Identities

Hanford Atomic Products Operation

Overview
Works: 3,894 works in 5,652 publications in 1 language and 22,432 library holdings
Genres: Abstracts  Periodicals  Methods (Music)  Charts, diagrams, etc  Bibliography 
Roles: Researcher
Classifications: QC801,
Publication Timeline
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Most widely held works by Hanford Atomic Products Operation
Plutonium abstracts( )

in English and held by 25 WorldCat member libraries worldwide

The green glow diffusion program by Morton Leopold Barad( Book )

1 edition published in 1962 in English and held by 25 WorldCat member libraries worldwide

Facilities for decontamination of laboratory equipment by O. L Olson( Book )

2 editions published in 1953 in English and held by 9 WorldCat member libraries worldwide

Evaluation of welded and seamless zirconium and zircaloy-2 tubing : interim report by S. H Bush( Book )

4 editions published in 1958 in English and held by 8 WorldCat member libraries worldwide

Review of power and heat reactor designs, domestic and foreign by E. R Appleby( Book )

4 editions published in 1963 in English and held by 8 WorldCat member libraries worldwide

Unclassified information from domestic and foreign literature from January 1952 through September 1963 is compiled. Design characteristics and current information on the status of the individual designs are given, along with references for the associated literature. SNAP systems, proposed reactors, and chemonuclear and test reactors with characteristics similar to power reactors are included. The designs are indexed by name, location, type, and some special characteristics. (D.C.W.)
The Hanford raindrop sampler and selected spectra by R. J Engelmann( Book )

2 editions published in 1962 in English and held by 8 WorldCat member libraries worldwide

A table to facilitate the calculation of likelihood ratio test statistics for hypotheses concerning grouped data by Wesley Lathrop Nicholson( Book )

3 editions published in 1961 in English and held by 7 WorldCat member libraries worldwide

The tables of f(N) = 2N log N, N = 1(1)5000 computed on an IBM 7090, is rounded off to three decimal places. An example of application of the tables to several sample problems is included. (J.R.D.)
A filament furnace for high temperature microscopy by H. W Newkirk( Book )

4 editions published between 1958 and 1959 in English and held by 7 WorldCat member libraries worldwide

The calcium fluoride-magnesium fluoride-lithium fluoride system by W. E Roake( Book )

4 editions published in 1955 in English and held by 6 WorldCat member libraries worldwide

Fission product release from uranium : effect of irradiation level( Book )

2 editions published in 1962 in English and held by 6 WorldCat member libraries worldwide

An experimental study was made to determine the influence of burnup on the fractional release of fission products from uranium metal at elevated temperatures. Neutron irradiation levels were varied from 2 x 10/sup 14/ nvt (6.7 x 10/sup 14/ Mwd/t) to 4 x 10/sup 20/ nvt (1340 Mwd/t) while all other conditions remained constant. Metal temperatures explored were 1000, 1200, and 1440 deg C. Bare uranium cylinders weighing approximately 12 grams were heated out-ofreactor and the liberated fractions of ten fission products plus uranium, plutonium, and neptunium were measured. The variation of the fractional releases of iodine, xenon, and cesium with irradiation level was shown, as was the invariance of the release of certain other elements with burnup. The uranium oxidation rate was found to increase with irradiation levels above l0/sup 18/ nvt. (auth)
Fission product release from uranium heated in air by R. K Hilliard( Book )

2 editions published in 1959 in English and held by 5 WorldCat member libraries worldwide

The release of fission products from small cylindrical specimens of normal uranium heated in an air stream was investigated in a laboratory study. The specimens were irradiated to 2.4 x 10/sup 14/ nvt and allowed to cool one to three in a resistance furnace with air flowing over the specimen The off-gas stream was scrubbed free of radioactive material by suitable traps. Analyses were performed on the volatilized pontion and on the dissolved residue to determine the fraction of fission products released. Analyses were made for I/ sup 131/, Te/sup 132/, Xe/sup 133/, Sr/sup 89, Cs, Ru/sup 103/, Ba/sup 140/, and Zr/sup 95/. Twenty-nine tests were performed with air and one with a helium atmosphere. The furnace temperature was varied from 425 to 1440 deg C while the time of heating varied from 2.5 to 232 minutes. The efficiencies of varions filter media for retaining air-boroe radioactive matter were investigated. An unsuccessful effort was made to separate the particulate from the elemental release. Data gathered in these tests were correlated to show the effects of temperature, time of heating and per cent of metal oxidized on the release coefficient for the fission products investigated (auth)
Nuclear safety in chemical and metallurgical processing of plutonium by E. D Clayton( Book )

3 editions published in 1961 in English and held by 5 WorldCat member libraries worldwide

A review was made of those types of criticality problems encountered in a typical plutonium processing and metal fabrication plant. A brief discussion is given of some of those criticality data which are of general interest in nuclear safety application, and of some of those data of limited application, but which are of special interest to specific processes. Curves are presented, based on multigroup diffusion theory, which show the estimated critical mass and infinite cylinder diameters for homogeneous PuO/sub 2/-water mixtures and the critical mass for Pu-- Al alloy. Applied methods of criticality control in plutonium processing and fuel element fabrication are reviewed. A list of typical administrative procedures, which have been used in effecting criticality control, is given. The proposed general program of studies for the new Hanford Plutonium Critical Mass Laboratory, which is being undertaken to obtain needed criticallty data for Pu solutions and precipitates of plutonium, is discussed. (auth)
Uniform aqueous corrosion of aluminum : effects of various ions( Book )

3 editions published in 1957 in English and held by 5 WorldCat member libraries worldwide

The most important variable in water quality on the uniform corrosion of Al was the pH. Solutions of distilled water containing phosphate ions and citrate ions were the only media which showed a definite specific ion effect. Phosphate inhibited the corrosion and citrate increased it. Oxalate ions appeared to increase corrosion, but the effect is not definitely demonstrated by the data. Corrosion was dependent only on pH in tap water, reactor process water, distilled water, and distilled water containing up to 100 ppm of chloride, nitrate, sulfate, bicarbonate, hydrogen peroxide, acetate, arsenate, silicate, dichromate, molybdate, and mixtures of these ions. Solutions of up to 10,000 ppm chloride in distilled water showed no specific ion effect upon uniform Al corrosion. The effects of 0 to 10 ppm of dichromate and phosphate ions were investigated over the range pH 4 to pH 7. Phosphate at 10 ppm inhibited corrosion in solutions containing up to 2 ppm of dichromate, but at 10 ppm dichromate the phosphate does not appear to inhibit corrosion. Also at 10 ppm dichromate, the effect of pH is diminished over the range pH 4 to pH 7. Corrosion rates varied with the flow rates of the test solutions at low flow rates, and were lowest at the lowest flow rates. This effect was attributed to the buildup of aluminate ion conconcentration in the lower flow systems. Short term corrosion tests at 92 deg C revealed major specific ion effects. Minor effects were lost in experimental uncertainties. The inhibiting effect of phosphate under these conditions has been shown to exist over longer exposures at higher temperatures. (auth)
Progress in treatment of a radioactive condensate waste by J. M Skarpelos( Book )

3 editions published in 1963 in English and held by 4 WorldCat member libraries worldwide

A waste stream decontamination process based on ion exchange was selected for development. The process is centered on ion-exchange technology developed during recent years in the Hanford Laboratories and other atomic energy research centers. Early attempts at small engineering scale application of ion- exchange technology resulted in less than satisfactory results when compared to laboratory data. The difficulties were traced to nonradioactive impurities in the wastes. Steam stripping and filtering successfully removed these impurities, and excellent decontamination of all significant isotopes except ruthenium was achieved by ion exchange. Satisfactory ruthenium decontamination was demonstrated on waste volumes up to about 1000 column volumes, and the capacity for other isotopes ranged from 10,000 to 20,000 column volumes. Improvement in ruthenium decontamination is needed to simplify operations and to improve economics. Although a largescale integrated process is yet to be demonstrated, a cost estimate of an ion-exchange process was made. The estimate of 50/1000 gal was based on a 2 ton/day fuels reprocessing plant which produces about 30,000 gal/day of condensate requiring treatment. The estimate was based on a process for alkaline condensate and it was assumed a process for acid condensate would cost about the same. This estimate is about /1000 gal less than the estimated cost for reevaporation. (auth)
Irradiation effects on uranium dioxide melting by J. A Christensen( Book )

3 editions published in 1962 in English and held by 4 WorldCat member libraries worldwide

Irradiated uranium dioxide with exposures to 11.25 at.% uranium burnup was examined microscopically at temperatures to 3000 deg C. Melting temperatures were measured and mass vaporization rates compared for UO₂ with 14 different exposures. (auth)
Steam-water critical flow from high pressure systems : interim report( Book )

3 editions published in 1964 in English and held by 4 WorldCat member libraries worldwide

In an earlier report, the problems associated with the prediction of the critical discharge rates of steam-water mixtures were discussed in detail. That report also gave the results of an experimental investigation of critical flows from long flow passages performed at low pressures. That investigation was later extended to consider short tubes, nozzles, and orifice flow configurations. The present work was undertaken to experimentally investigate the critical discharge phenomenon at higher pressures and to use the data gathered to critically evaluate the various proposed critical flow models. The purpose of this interim report is to describe in detail the apparatus assembled for this investigation and to report preliminary findings regarding the critical discharge rates from a 0.5-inch diameter flow passage
Measuring and correlating neutron exposure and damage in graphite by Ronald E Dahl( Book )

3 editions published in 1963 in English and held by 4 WorldCat member libraries worldwide

Portable dose-rate integrator -- Mark I by A. N Iverson( Book )

4 editions published in 1960 in English and held by 2 WorldCat member libraries worldwide

Reactor statistics : Section 3, April 1961--May 15, 1962. Reactor Simulation Study, Reactor 4( )

6 editions published in 1962 in English and held by 0 WorldCat member libraries worldwide

This discussion and attached summary report illustrate the type of information that was in data processing machine language and available to those who require it. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the cateogry defined by the function number code. The second is a summary of the data, in terms of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed within a basic function class, the associated delay total, and the number of tubes involved for those functions where a delineation by tube count may be of interest. The function code numbers relate directly to the definitions of the hours expended for charge-discharge, rupture removal, tube leak repair, tube replacement, and so forth. These definitive classes are taken from the distribution records supplied by the various reactor analysts and summarized by the Reports and Statistics group in the IPD Production Operation
Status of special reactor process tube loadings, June 1, 1965( )

7 editions published in 1965 in English and held by 0 WorldCat member libraries worldwide

This report shows the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials
 
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Alternative Names
General Electric Company. Hanford Atomic Products Operation

Languages
English (80)