WorldCat Identities

Hanford Atomic Products Operation

Overview
Works: 3,753 works in 5,084 publications in 1 language and 7,530 library holdings
Genres: Periodicals  Abstracts  Charts, diagrams, etc 
Roles: Researcher
Classifications: TD195.N85,
Publication Timeline
Key
Publications about Hanford Atomic Products Operation Publications about Hanford Atomic Products Operation
Publications by Hanford Atomic Products Operation Publications by Hanford Atomic Products Operation
Most widely held works by Hanford Atomic Products Operation
Plutonium abstracts ( )
in English and held by 20 WorldCat member libraries worldwide
HW by U.S. Atomic Energy Commission ( )
in English and held by 17 WorldCat member libraries worldwide
A review of research on plutonium releases during overheating and fires by J Mishima ( )
3 editions published in 1964 in English and held by 15 WorldCat member libraries worldwide
Facilities for decontamination of laboratory equipment by O. L Olson ( )
2 editions published in 1953 in English and held by 15 WorldCat member libraries worldwide
A table to facilitate the calculation of likelihood ratio test statistics for hypotheses concerning grouped data by Wesley Lathrop Nicholson ( )
3 editions published in 1961 in English and held by 14 WorldCat member libraries worldwide
A study of mortality from congenital malformation for Benton County, Washington by R. C Henle ( )
3 editions published in 1960 in English and held by 14 WorldCat member libraries worldwide
Evaluation of radiological conditions in the vicinity of Hanford for ... ( )
in English and held by 14 WorldCat member libraries worldwide
Meteorology as related to waste disposal and weapons tests by J. J Fuquay ( )
3 editions published in 1957 in English and held by 14 WorldCat member libraries worldwide
Some measurements of the deposition of matter and its relation to diffusion from a continuous point source in a stable atmosphere by C. L Simpson ( )
2 editions published in 1961 in English and held by 14 WorldCat member libraries worldwide
Mechanisms and kinetics of uranium corrosion and uranium core fuel element ruptures in water and steam by V. H Troutner ( )
4 editions published in 1960 in English and held by 14 WorldCat member libraries worldwide
The mechanisms and kinetics of uranium corrosion and fuel element ruptures were investigated in water and steam at 170 to 500 deg C and at 100 to 2800 psig. The fuel element samples were coextruded Zircaloy-clad uranium-core rods and tubes which were defected prior to exposure. Uranium corrosion was found to be the sum of two processes; direct oxidation by water, and oxidation of uranium hydride intermediate. Fuel element ruptures occur in two stages; an initial induction period followed by an accelerating corrosion of the core causing the cladding to blister, swell, and fracture. Uranium corrosion and fuel element ruptures were examined with respect to temperature, pressure, steam versus liquid water, heat treatment, carbon content of uranium, zirconium content of uranium, cladding thickness, fuel geometry, annular spacings, defect geometry and size, coolant flow, hydriding of Zircaloy components, and irradiation effects. (auth)
Experimental evaluation of the combustion hazard to the experimental gas-cooled reactor-preliminary burning rig experiments by Ronald E Dahl ( )
4 editions published in 1961 in English and held by 13 WorldCat member libraries worldwide
An assembly was constructed which simulated the moderator coolant annulus in the Experimental Gas-Cooled Reactor. This assembly was preheated to various temperatures and air was passed through the coolant annulus. Under certain conditions it was demonstrated that self-sustained combustion of the graphite could occur. Rates of temperature rise were generally less than 1 deg C/ min until the graphite temperature exceeded 700 deg C and then rise rates became very high. In these cxperimcnts, the assembly was not operated in such a manner as to give ignition temperatures eharaeteristic of the EGCR. These tests were designed only to investigate the effects of changing such parameters as the rate of coolant flow, air humidity, prior oxidation on the graphite, and air inlet temperature. A later series of experiments to more closely duplicate the EGCR operating conditions was completed and will be reported in a second report, HW- 71182. (auth)
Approach to critical and calibration experiments in the Plutonium Recycle Critical Facility by R. A Bennett ( )
3 editions published in 1964 in English and held by 13 WorldCat member libraries worldwide
Strontium-90 concentrations in the Hanford environs by W. B Silker ( )
2 editions published in 1958 in English and held by 13 WorldCat member libraries worldwide
A parametric study of the gas-cooled reactor concept by Hanford Atomic Products Operation ( )
2 editions published in 1958 in English and held by 13 WorldCat member libraries worldwide
The H-1 high temperature graphite irradiation experiment by J. M Davidson ( )
4 editions published in 1961 in English and held by 13 WorldCat member libraries worldwide
A high temperature graphite irradiation experinient was performed in the GETR core to determine the effects of differences in manufacturing, formulation, and graphitization temperatures on radiation-induced eontraction. The experiment was performed at temperatures of 800 to 1200 deg C in an intense fast neutron flux. The maximum integrated exposure of the sample positions was 3.2 x 10?sup 21/ nvt, E> 0.18 Mev, corresponding to approximately 24,000 MWD/AT in a conventional graphite-moderated reactor. All the graphites tested, with the exception of the controls, were needle coke filler, coal tar pitch binder graphites varying mn particle size, graphitization temperature, and impregnation. From theoretical and experitnental considerations, the formulations and treatments were expected to result in a relatively stable graphite in the direction transverse to extrusion. For comparison of the experimental results to existing experience, a conventional graphite, CSF, was used at each irradiation position. The results showed that the graphite most stable to contraction was graphaitized at a high temperature(>3100hC) and made from small particle size (all flour) filler. In all cases, the needle coke graphite contracted at a lower rate than the CSF graphite. Differences attributable to the size of extrusion and/or post graphitization cooling rate were discerned readily. Auxil iary to the purposes of the experiment, the apparent thermnal neutron cross section for Co⁵⁸ (plus Co /sup 58m) was determined. Co⁵⁸ and Co/sup 58m/ are the products of the Ni⁵⁸ (n, p) reaction, which is used widely for fast flux monitoring. Both have large thermal neutron capture cross sections which must be accounted for to prevent error in fast neutron dosimetry. In this experiment, a value was determined for the apparent burn-out cross section of 3750 barns. (auth)
Epi-cadmium fission in U-235 by E. D Clayton ( )
2 editions published in 1955 in English and held by 12 WorldCat member libraries worldwide
Confinement and collection of UO₂ fines from a shearing operation by G Rey ( )
3 editions published in 1960 in English and held by 12 WorldCat member libraries worldwide
Selective reduction of plutonium(VI) to plutonium(IV) in a plutonium(IV-VI) nitric acid solution by M. H Campbell ( )
4 editions published in 1961 in English and held by 12 WorldCat member libraries worldwide
Cation effects on the distribution of uranium in the system aluminum-aluminum chloride-alkali chloride by R. H Moore ( )
3 editions published in 1960 in English and held by 12 WorldCat member libraries worldwide
Xenon instability in graphite reactors by G. C Fullmer ( )
3 editions published in 1961 in English and held by 12 WorldCat member libraries worldwide
 
moreShow More Titles
fewerShow Fewer Titles
Audience Level
0
Audience Level
1
  Kids General Special  
Audience level: 0.84 (from 0.00 for The Hanfor ... to 1.00 for Radiation ...)
Alternative Names
General Electric Company. Hanford Atomic Products Operation
Languages
English (72)