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  • Validation of absolute axial neutron flux distribution calculations with MCNP with [sup]197Au(n,gamma) [sup]198Au reaction rate distribution measurements at the JSI TRIGA Mark II reactor
    Radulović, Vladimir ...
    The calculation of axial neutron flux distributions with the MCNP code at the JSI TRIGA Mark II reactor has been validated with experimental measurements of the 197Au(n,)198Au reaction rate. The ... calculated absolute reaction rate values, scaled according to the reactor power and corrected for the flux redistribution effect, are in good agreement with the experimental results. The effect of different cross-section libraries on the calculations has been investigated and shown to be minor.
    Source: Applied Radiation and Isotopes. - ISSN 0969-8043 (Vol. 84, 2014, str. 57-65)
    Type of material - article, component part
    Publish date - 2014
    Language - english
    COBISS.SI-ID - 27309095
    DOI