Evaluation of Zirconium Hydride as Moderator in Integral, Boiling Water-Superheat Reactors

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Description

This report summarizes the results and conclusions of a study made to evaluate the merits of using zirconium hydride as a solid moderator in an integral boiling water-nuclear superheat reactor of the pressure vessel type.

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vii, 129 p. : ill., tables ; 28 cm.

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Gylfe, J. D.; Rood, H.; Greenleaf, J.; Balkwill, K.; Prem, L. & Goldfisher, L. March 1, 1962.

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This report summarizes the results and conclusions of a study made to evaluate the merits of using zirconium hydride as a solid moderator in an integral boiling water-nuclear superheat reactor of the pressure vessel type.

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vii, 129 p. : ill., tables ; 28 cm.

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  • March 1, 1962

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  • Dec. 17, 2018, 8:41 a.m.

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  • Jan. 7, 2019, 1:28 p.m.

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Gylfe, J. D.; Rood, H.; Greenleaf, J.; Balkwill, K.; Prem, L. & Goldfisher, L. Evaluation of Zirconium Hydride as Moderator in Integral, Boiling Water-Superheat Reactors, report, March 1, 1962; Canoga Park, California. (digital.library.unt.edu/ark:/67531/metadc957975/: accessed January 20, 2019), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.