Volume 9, Issue 3 (March 2012)

    Design and Testing of a Boron Carbide Capsule for Spectral Tailoring in Mixed-Spectrum Reactors

    (Received 11 May 2011; accepted 20 November 2011)

    Published Online: 2012

    CODEN: JAIOAD

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    Abstract

    A boron carbide capsule has been designed and used for spectral-tailoring experiments at the TRIGA reactor at Washington State University. Irradiations were conducted in pulsed mode and in continuous operation for up to 4 h. A cadmium cover was used to reduce thermal heating. The neutron spectrum calculated with the Monte Carlo N-particle transport code was found to be in good agreement with reactor dosimetry measurements using the STAY’SL computer code. The neutron spectrum resembles that of a fast reactor. The design of a capsule using boron carbide fully enriched in 10B shows that it is possible to produce a neutron spectrum similar to that of 235U fission.


    Author Information:

    Greenwood, L. R.
    Pacific Northwest National Laboratory, Richland, WA

    Wittman, R.
    Pacific Northwest National Laboratory, Richland, WA

    Pierson, B. P.
    Univ. of Michigan, Ann Arbor, MI

    Metz, L. A.
    Pacific Northwest National Laboratory, Richland, WA

    Payne, R.
    Pacific Northwest National Laboratory, Richland, WA

    Finn, E. C.
    Pacific Northwest National Laboratory, Richland, WA

    Friese, J. I.
    Pacific Northwest National Laboratory, Richland, WA


    Stock #: JAI103959

    ISSN: 1546-962X

    DOI: 10.1520/JAI103959

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    Title Design and Testing of a Boron Carbide Capsule for Spectral Tailoring in Mixed-Spectrum Reactors
    Symposium , 0000-00-00
    Committee E10