Abstract:Neutron spectrum information in reactor core and around of ex-vessel reactor needs to be known with a certain degree of accuracy to support the development of fuels, materials, and other components. The most common method to determine neutron spectra is by utilizing the radioactivation of dosimeter materials. This report presents the evaluation of neutron flux incident on M3 dosimeter sets which were irradiated outside the reactor vessel, as well as the validation of neutron spectrum calculation. Al capsules c… Show more
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