Preliminary Solution Critical Experiments for the High-Flux Isotope Reactor

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Description

Report containing experiments conducted at the Oak Ridge National Laboratory's Critical Experiments Facility. These experiments involved "determining the critical parameters of the assembly with varying amounts of neutron absorber in the D20 reflector, measuring the relative neutron flux distribution for various conditions of reflector poison and fissile solution concentration, determining the ratio of the absolute thermal-neutron flux in the center of the assembly to the power in the fissile solution , and determining the effect on reactivity of reducing the hydrogen density in the central region of the assembly" (p. 1).

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v, 81 p. : ill. ; 28 cm.

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Fox, J. K.; Magnuson, D. W. & Gilley, L. W. June 12, 1963.

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This report is part of the collection entitled: Technical Report Archive and Image Library and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 101 times. More information about this report can be viewed below.

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Description

Report containing experiments conducted at the Oak Ridge National Laboratory's Critical Experiments Facility. These experiments involved "determining the critical parameters of the assembly with varying amounts of neutron absorber in the D20 reflector, measuring the relative neutron flux distribution for various conditions of reflector poison and fissile solution concentration, determining the ratio of the absolute thermal-neutron flux in the center of the assembly to the power in the fissile solution , and determining the effect on reactivity of reducing the hydrogen density in the central region of the assembly" (p. 1).

Physical Description

v, 81 p. : ill. ; 28 cm.

Notes

"UC-80 Reactor Technology"

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  • OCLC: 85271954
  • SuDoc Number: Y 3.At 7:22/ORNL-3359
  • Report No.: ORNL-3359
  • Grant Number: W-7405-eng-26
  • Archival Resource Key: ark:/67531/metadc100430

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Technical Report Archive and Image Library

The Technical Report Archive & Image Library (TRAIL) identifies, acquires, catalogs, digitizes and provides unrestricted access to U.S. government agency technical reports. The mission of TRAIL is to ensure preservation, discoverability, and persistent open access to government technical publications regardless of form or format.

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  • June 12, 1963

Added to The UNT Digital Library

  • Jan. 31, 2014, 11:57 a.m.

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  • March 15, 2018, 1:08 p.m.

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Fox, J. K.; Magnuson, D. W. & Gilley, L. W. Preliminary Solution Critical Experiments for the High-Flux Isotope Reactor, report, June 12, 1963; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc100430/: accessed May 13, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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