STP457

    Neutron Dosimetry for Fast-Reactor Irradiation and Surveillance Testing

    Published: Jan 1969


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    Abstract

    Dosimetry for fast-reactor irradiation experiments introduces problems not encountered in thermal reactors. The difference in neutron spectrum causes quite different responses among candidate dosimetry materials. Moreover, the damage modes in fast-reactor irradiations and in thermal reactor irradiations may be quite different. This work is aimed at developing adequate methods for spectral determinations, neutron dosimetry, and damage correlation for fast-reactor tests.

    Spectral determinations have been performed using a multiple foil activation technique (SAND-II). The SAND-II analysis provides integral neutron flux data with an absolute accuracy of 10 to 30 percent. Intercomparison of analytical results, neutron spectrometer results, and SAND-II determinations indicate reasonable agreement among all three techniques.

    While the SAND-II technique provides fluence data, threshold and resonance monitors are simpler to use. A slight modification of monitoring procedures used in thermal reactors suffices for fast-reactor dosimetry. Results from activation monitors in EBR-II and ECEL indicate the feasibility of the monitoring methods.

    Damage correlation techniques depend on the mechanisms causing damage. Two of the mechanisms causing property changes during fast-reactor irradiations are displacement production and helium generation by neutron reactions. The fluence dependence for these mechanisms illustrate the need for correlation analyses.

    Keywords:

    radiation effects, neutrons, irradiations, reactors, neutron dosimetry, neutron spectra, tests, evaluation


    Author Information:

    Yoshikawa, H. H.
    Unit Manager and Research Associate, Battelle Memorial Institute, Pacific Northwest Laboratory, Richland, Wash.

    McElroy, W. N.
    Unit Manager and Research Associate, Battelle Memorial Institute, Pacific Northwest Laboratory, Richland, Wash.


    Paper ID: STP41856S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP41856S


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