The development and properties of an oxidation-resistant coating for uranium

Buddery, J.H.; Clark, Malcolm; Pearce, R.; Stobbs, J.J.

doi:10.1016/0022-3115(64)90038-8

Cited by 24 publications

(6 citation statements)

References 4 publications

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“…This pattern of behavior is consistent with the following theory based on observed properties of uranium-aluminum intermetallic compounds prepared by different techniques (Le Claire and Bear 1956;Buddery et al 1964;Giles and Tavender 1967;Bland 1968;Subramanyam et al 1985). Uranium is not distributed completely uniformly in the preparation but may exist as "islands" of unreacted uranium.…”

Section: Models Used To Interpret Bioassay Datasupporting

confidence: 87%

A Comprehensive Dose Reconstruction Methodology for Former Rocketdyne/Atomics International Radiation Workers

Boice

Leggett²,

Ellis³

et al. 2006

Health Physics

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Incomplete radiation exposure histories, inadequate treatment of internally deposited radionuclides, and failure to account for neutron exposures can be important uncertainties in epidemiologic studies of radiation workers. Organ-specific doses from lifetime occupational exposures and radionuclide intakes were estimated for an epidemiologic study of 5,801 Rocketdyne/Atomics International (AI) radiation workers engaged in nuclear technologies between 1948 and 1999. The entire workforce of 46,970 Rocketdyne/AI employees was identified from 35,042 Kardex work histories cards, 26,136 electronic personnel listings, and 14,189 radiation folders containing individual exposure histories. To obtain prior and subsequent occupational exposure information, the roster of all workers was matched against nationwide dosimetry files from the Department of Energy, the Nuclear Regulatory Commission, the Landauer dosimetry company, the U.S. Army, and the U.S. Air Force. Dosimetry files of other worker studies were also accessed. Computation of organ doses from radionuclide intakes was complicated by the diversity of bioassay data collected over a 40-y period (urine and fecal samples, lung counts, whole-body counts, nasal smears, and wound and incident reports) and the variety of radionuclides with documented intake including isotopes of uranium, plutonium, americium, calcium, cesium, cerium, zirconium, thorium, polonium, promethium, iodine, zinc, strontium, and hydrogen (tritium). Over 30,000 individual bioassay measurements, recorded on 11 different bioassay forms, were abstracted. The bioassay data were evaluated using ICRP biokinetic models recommended in current or upcoming ICRP documents (modified for one inhaled material to reflect site-specific information) to estimate annual doses for 16 organs or tissues taking into account time of exposure, type of radionuclide, and excretion patterns. Detailed internal exposure scenarios were developed and annual internal doses were derived on a case-by-case basis for workers with committed equivalent doses indicated by screening criteria to be greater than 10 mSv to the organ with the highest internal dose. Overall, 5,801 workers were monitored for radiation at Rocketdyne/AI: 5,743 for external exposure and 2,232 for internal intakes of radionuclides; 41,169 workers were not monitored for radiation. The mean cumulative external dose based on Rocketdyne/AI records alone was 10.0 mSv, and the dose distribution was highly skewed with most workers experiencing low cumulative doses and only a few with high doses (maximum 500 mSv). Only 45 workers received greater than 200 mSv while employed at Rocketdyne/AI. However, nearly 32% (or 1,833) of the Rocketdyne/AI workers had been monitored for radiation at other nuclear facilities and incorporation of these doses increased the mean dose to 13.5 mSv (maximum 1,005 mSv) and the number of workers with >200 mSv to 69. For a small number of workers (n=292), lung doses from internal radionuclide intakes were relatively high (mean 106 mSv; maximum 3,560...

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Section: Models Used To Interpret Bioassay Datasupporting

confidence: 87%

A Comprehensive Dose Reconstruction Methodology for Former Rocketdyne/Atomics International Radiation Workers

Boice

Leggett²,

Ellis³

et al. 2006

Health Physics

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“…As deposition of carbon on uranium dioxide from car-bon monoxide only occurs when the carbon dioxide content of the gas is < 1% (1~), the most likely site for reaction [3] will be within the cracks in the oxide, which constitute stagnant regions where the carbon dioxide content will be low; the association of the second phase (which has been shown to be directly connected with the carbon monoxide reaction) with cracks in the oxide supports this view. And the existence of a lower carbon content in the nonadherent oxide is also consistent since this oxide would consist of the outer layers that were near the widest parts of the cracks where the carbon dioxide content of the gas would be higher and the carbon deposition rate consequently low.…”

Section: ~176mentioning

confidence: 96%

“…nd where Ng is the number of donors, Na the number of aceeptors, and n~ the electron concentration in the conduction band. Combining [2] and [3], we obtain for predominant donor doping Vd N~ + (N~ 2 + 4hi 2) 2/2…”

Section: Appendixmentioning

confidence: 99%

“…The latter obtained similar carbon levels which were also independent of temperature. However, his assumption that carbon deposition results from the reaction U -5 CO~-~ U02 + C [2] is not wholly justified on the experimental evidence, and it seems more likely that the reaction leading to carbon deposition is U -5 2CO -> UO2 + 2C [3] from the carbon monoxide produced by reaction [1].…”

Section: ~176mentioning

confidence: 99%

“…From the first simplest Hildebrand electrode (1) until the more recent types, the hydrogen electrode has undergone considerable modifications (2) to improve its performances for accurate measurements in the area of the electrochemical thermodynamics and kinetics (3).…”

Section: Laboratory Of Electrochemistry and Metallurgy University Of ...mentioning

confidence: 99%

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The Oxidation Mechanism of Pure Uranium in Carbon Dioxide Between 350° and 650°C

Stobbs¹

1965

J. Electrochem. Soc.

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Weight gain/time curves obtained on a thermobalance are related to metallographic observations of the oxide. It is found that the oxide is initially protective, but as a result of nonuniform oxidation and cracking the oxidation rate accelerates until finally a linear rate law is obeyed. In the early stages of oxidation a separate layer of oxide grows at the oxide‐gas interface, but soon attains a limiting thickness of a few thousand Angstroms and does not influence the over‐all oxidation behavior. Carbon monoxide formed from the reaction between uranium and carbon dioxide reacts further in the cracks in the oxide.

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