Experience with the use of the 93Nb(n,n')93sup(m)Nb reaction for routine monitoring of materials irradiation experiments

The use of the 93Nb(n,n') reaction with long half life and low energy threshold holds out much promise as a routine fast neutron and hence damage monitor in materials irradiation dosimetry. Recent UK experience in a large and varied number of metallurgical irradiation experiments using this reaction in conjunction with more conventional activation monitors suggests that there may still be systematic discrepancies in the nuclear data associated with this reaction, particularly in the domain of the reaction cross sections. Experience has shown that previous practical difficulties using this reaction can be simply overcome and therefore impetus should be given quickly to improving our knowledge of its cross section. (author)