A Proposed Fuel Assay Reactor

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Description

There is a need for a special type of nuclear reactor that can test fuel elements nondestructively to determine the total amounts and the distributions of both fissionable and parasitically absorbing materials in completed, unirradiated fuel elements. Such a reactor, called the Fuel Assay Reactor, is proposed. Theoretical considerations are presented to show the reactivity changes that result from the insertion of both fissionable and absorbing material into a central test hole. The choice of moderator depends upon the size of material to be tested. For testing small pellets of fissionable material, a light-water- moderated assembly is advantageous because of ... continued below

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17 p.

Creation Information

Martens, F. H. & Sandmeier, H. A. August 1, 1960.

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Description

There is a need for a special type of nuclear reactor that can test fuel elements nondestructively to determine the total amounts and the distributions of both fissionable and parasitically absorbing materials in completed, unirradiated fuel elements. Such a reactor, called the Fuel Assay Reactor, is proposed. Theoretical considerations are presented to show the reactivity changes that result from the insertion of both fissionable and absorbing material into a central test hole. The choice of moderator depends upon the size of material to be tested. For testing small pellets of fissionable material, a light-water- moderated assembly is advantageous because of its small critical mass; for large, completed fuel elements a graphite or heavy-watermoderated system is more suitable. An internal reflector gives increased sensitivity in the center and allows enough space surrounding the test element so that spectral changes in a nonfuel region may be produced in order to discriminate between fissionable and absorbing materials. The factors determining maximum sensitivity are discussed, as are several reactivity measurement methods suitable for testing fuel elements. The limits of accuracy are governed by the statistical variation of the neutron population within the reactor core. The theoretical limits of accuracy of all methods have the same order of magnitude, but the automatic-flux-level method appears to have advantages over the pile-period and oscillator methods for this purpose. (auth)

Physical Description

17 p.

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NTIS

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

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  • Report No.: ANL-6203
  • Grant Number: W-31-109-ENG-38
  • DOI: 10.2172/4138376 | External Link
  • Office of Scientific & Technical Information Report Number: 4138376
  • Archival Resource Key: ark:/67531/metadc872453

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • August 1, 1960

Added to The UNT Digital Library

  • Sept. 16, 2016, 12:32 a.m.

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  • Oct. 12, 2017, 2:21 p.m.

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Martens, F. H. & Sandmeier, H. A. A Proposed Fuel Assay Reactor, report, August 1, 1960; Illinois. (digital.library.unt.edu/ark:/67531/metadc872453/: accessed November 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.