Chemical Engineering Division Reactor Fuels and Materials Chemistry Research: July 1976-September 1977

One of 1,237 reports in the series: Argonne National Laboratory Reports available on this site.

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Description

Report describing the research and development activities related to reactor fuels and fast-reactor programs conducted by the Argonne National Laboratory Chemical Engineering Division.

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viii, 108 p. : charts, photographs, tables

Creation Information

Cafasso, F. A.; Leibowitz, L.; McPheeters, C. C. & Johnson, C. E. July 1978.

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This report is part of the collection entitled: Technical Report Archive and Image Library and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 119 times , with 6 in the last month . More information about this report can be viewed below.

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  • Main Title: Chemical Engineering Division Reactor Fuels and Materials Chemistry Research: July 1976-September 1977
  • Added Title: ANL (Series)
  • Added Title: Argonne National Laboratory Report ANL-78-15
  • Series Title: Argonne National Laboratory Reports

Description

Report describing the research and development activities related to reactor fuels and fast-reactor programs conducted by the Argonne National Laboratory Chemical Engineering Division.

Physical Description

viii, 108 p. : charts, photographs, tables

Notes

Digitized from microfiche (2).

Some parts of this report may be illegible, depending on the quality of the microfiche.

Partial abstract: "This report describes research and development activities conducted in support of fast-reactor programs during the period July 1976 - September 1977. Reactor safety studies were directed primarily toward obtaining high-temperature physical property data for use in reactor safety analyses. Spectrographic data and an oxygen-potential model were used to calculate thermodynamic properties applicable to the equations of state of uranium-plutonium dioxide and uranium dioxide. Work was continued on the compilation of standard sets of property data on reactor fuels and materials. The viscosity of molten aluminum and the thermal diffusivity of molten uranium dioxide were measured as functions of temperature. Modeling and chemical-interaction studies related to post-accident heat removal were conducted.
The efforts in sodium technology supported the LMFBR program. Studies were conducted to explore the feasibility of upgrading the quality of commercial-grade sodium and sodium from decommissioned reactors to provide new sources of reactor-grade sodium. [...]
Work in the area of fuels and materials chemistry was conducted in support of the GCFR program."

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Technical Report Archive and Image Library

This selection of materials from the Technical Report Archive and Image Library (TRAIL) includes hard-to-find reports published by various government agencies. The technical publications contain reports, images, and technical descriptions of research performed for U.S. government agencies. Topics range from mining, desalination, and radiation to broader physics, biology, and chemistry studies. Some reports include maps, foldouts, blueprints, and other oversize materials.

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Creation Date

  • July 1978

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Added to The UNT Digital Library

  • Aug. 4, 2015, 8:33 a.m.

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  • June 22, 2017, 7:40 p.m.

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Cafasso, F. A.; Leibowitz, L.; McPheeters, C. C. & Johnson, C. E. Chemical Engineering Division Reactor Fuels and Materials Chemistry Research: July 1976-September 1977, report, July 1978; Argonne, Illinois. (digital.library.unt.edu/ark:/67531/metadc283286/: accessed June 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.