Criticality facilities and programs at Sandia National Laboratories

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The reactor facilities at Sandia National Laboratories have hosted a number of reactors and critical experiments. A critical experiment is currently being done to support an ongoing investigation by the US Department of Energy of the consequences of taking fuel burnup into account in the design of spent fuel transportation packages. A series of experiments, collectively called the Spent Fuel Safety Experiment (SFSX), has been devised to provide integral benchmarks for testing computer-generated predictions of spent fuel behavior. A set of experiments is planned in which sections of unirradiated fuel rods are interchanged with similar sections of spent pressurized water ... continued below

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5 p.

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Harms, G.A.; Davis, F.J. & Ford, J.T. December 31, 1995.

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this article can be viewed below.

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  • Sandia National Laboratories
    Publisher Info: Sandia National Labs., Albuquerque, NM (United States)
    Place of Publication: Albuquerque, New Mexico

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Description

The reactor facilities at Sandia National Laboratories have hosted a number of reactors and critical experiments. A critical experiment is currently being done to support an ongoing investigation by the US Department of Energy of the consequences of taking fuel burnup into account in the design of spent fuel transportation packages. A series of experiments, collectively called the Spent Fuel Safety Experiment (SFSX), has been devised to provide integral benchmarks for testing computer-generated predictions of spent fuel behavior. A set of experiments is planned in which sections of unirradiated fuel rods are interchanged with similar sections of spent pressurized water reactor (PWR) fuel rods in a critical assembly. By determining the critical size of the arrays, one can obtain benchmark data for comparison with criticality safety calculations. The SFSX provides a direct measurement of the reactivity effects of spent PWR fuel using a well-characterized, spent fuel sample. The SFSX also provides an experimental measurement of the end-effect, i.e., the reactivity effect of the variation of the burnup profile at the ends of PWR fuel rods. The design of the SFSX is optimized to yield accurate benchmark measurements of the effects of interest, well above experimental uncertainties.

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5 p.

Notes

INIS; OSTI as DE96007706

Source

  • Expert meeting on experimental needs in criticality safety, Albuquerque, NM (United States), 25-26 Sep 1995

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  • Other: DE96007706
  • Report No.: SAND--96-0325C
  • Report No.: CONF-9509297--2
  • Grant Number: AC04-94AL85000
  • Office of Scientific & Technical Information Report Number: 207429
  • Archival Resource Key: ark:/67531/metadc665709

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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

  • December 31, 1995

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

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  • April 14, 2016, 3:28 p.m.

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Harms, G.A.; Davis, F.J. & Ford, J.T. Criticality facilities and programs at Sandia National Laboratories, article, December 31, 1995; Albuquerque, New Mexico. (digital.library.unt.edu/ark:/67531/metadc665709/: accessed October 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.