The spent fuel safety experiment

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Description

The Department of Energy is conducting an ongoing investigation 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 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 ... continued below

Physical Description

8 p.

Creation Information

Harmms, G.A.; Davis, F.J. & Ford, J.T. July 1, 1995.

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This report 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 report 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 Department of Energy is conducting an ongoing investigation 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 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 integral reactivity worth of the spent fuel can be assessed by comparing the measured delayed critical fuel loading with and without spent fuel. An analytical effort to model the experiments and anticipate the core loadings required to yield the delayed critical conditions runs in parallel with the experimental effort.

Physical Description

8 p.

Notes

INIS; OSTI as DE95015090

Source

  • 5. international conference on nuclear criticality safety, Albuquerque, NM (United States), 17-22 Sep 1995

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Identifier

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  • Other: DE95015090
  • Report No.: SAND--95-1509C
  • Report No.: CONF-9509100--17
  • Grant Number: AC04-94AL85000
  • DOI: 10.2172/102184 | External Link
  • Office of Scientific & Technical Information Report Number: 102184
  • Archival Resource Key: ark:/67531/metadc624855

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Office of Scientific & Technical Information Technical Reports

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Creation Date

  • July 1, 1995

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

Description Last Updated

  • April 14, 2016, 7:01 p.m.

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Citations, Rights, Re-Use

Harmms, G.A.; Davis, F.J. & Ford, J.T. The spent fuel safety experiment, report, July 1, 1995; Albuquerque, New Mexico. (digital.library.unt.edu/ark:/67531/metadc624855/: accessed September 21, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.