SODIUM REACTOR EXPERIMENT (SRE) SHIELDING EVALUATION FOR THERMAL NEUTRON STREAMING AT REACTOR VESSEL COOLANT PIPE PENETRATIONS

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The experimental program performed in the SRE auxiliary and main primary galleries was part of a program to determine the adequacy of the shielding configuration for the SRE. The work discussed in this report is concerned with analysis of neutron streaming at coolant pipe penetrations of the reactor vessel, analysis of the shielding required, testing and evaluation of recommended shielding, and measurement and correlation of neutron streaming in labyrinths with theory. The activation analysis method using zinc sheets which was developed for the program of determining thermal neutron streaming in the SRE primary galleries was proven to be versatile, accurate, ... continued below

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Pages: 56

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Anderson, F. D. October 31, 1959.

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Description

The experimental program performed in the SRE auxiliary and main primary galleries was part of a program to determine the adequacy of the shielding configuration for the SRE. The work discussed in this report is concerned with analysis of neutron streaming at coolant pipe penetrations of the reactor vessel, analysis of the shielding required, testing and evaluation of recommended shielding, and measurement and correlation of neutron streaming in labyrinths with theory. The activation analysis method using zinc sheets which was developed for the program of determining thermal neutron streaming in the SRE primary galleries was proven to be versatile, accurate, and reliable. A modified form of the theoretical method of Price, Horton, and Spinney, used to determine neutron scattring through labyrinths, was found to agree favorably with the experimental results obtained from the SRE primary galleries. The theoretical attenuation method used no determine the neutron shield configuration installed in the auxiliary primary gallery was found to give an overestimate of the actual attenuation properties of this shield. The neutron shield configuration installed in the auxiliary primary gallery proved to be adequate in reducing the thermal neutron streaming flux to an acceptable level. It is concluded that both SRE primary galleries are now adequately shielded to prevent excessive neutron- induced activation of the components and equipment located therein. (auth)

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Pages: 56

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  • Other Information: Orig. Receipt Date: 31-DEC-60

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  • Report No.: NAA-SR-3990
  • Grant Number: AT-11-1-GEN-8
  • DOI: 10.2172/4233098 | External Link
  • Office of Scientific & Technical Information Report Number: 4233098
  • Archival Resource Key: ark:/67531/metadc1020968

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Office of Scientific & Technical Information Technical Reports

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  • October 31, 1959

Added to The UNT Digital Library

  • Oct. 15, 2017, 10:09 p.m.

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  • Jan. 22, 2018, 11:26 a.m.

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Anderson, F. D. SODIUM REACTOR EXPERIMENT (SRE) SHIELDING EVALUATION FOR THERMAL NEUTRON STREAMING AT REACTOR VESSEL COOLANT PIPE PENETRATIONS, report, October 31, 1959; Canoga Park, California. (digital.library.unt.edu/ark:/67531/metadc1020968/: accessed October 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.