STP286

    Measurement of the Energy Absorbed from Pile Neutrons

    Published: Jan 1960


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    Abstract

    The energy absorbed by materials in a pile may be measured directly by calorimetric methods. In view of the difficulties of in-pile calorimetry, however, it is of interest to develop other methods of measurement. Neutron threshold and resonance reactions provide a means for estimating the neutron spectrum in the pile and may be used to calculate the energy absorbed from neutrons. In order to test the accuracy of this method, threshold and resonance detectors were placed in various positions in the Oak Ridge National Laboratory Graphite Reactor and the results were compared to calorimetric measurements. Two experimental holes in the reactor were used, hole 19 and hole 51. Hole 19 is a 2-in. circular hole in the graphite moderator running transverse to the cylindrical fuel elements, which are spaced 8 in. apart in a square lattice. Hole 51 is a 4 by 4-in. hole also running transverse to the fuel rods and contains a cylinder of enriched uranium. The uranium cylinder or “converter” increases the flux of fission neutrons while depressing the thermal neutron flux.


    Author Information:

    Binder, D.
    U. S. Atomic Energy Commission, Oak Ridge, Tenn.

    Bopp, C. D.
    U. S. Atomic Energy Commission, Oak Ridge, Tenn.

    Towns, R. L.
    U. S. Atomic Energy Commission, Oak Ridge, Tenn.


    Paper ID: STP46370S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP46370S


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