Abstract
The validity of the 107Ag(n, n′)107mAg reaction for reactor neutron dosimetry has been examined through an irradiation experiment using the standard neutron field in the “YAYOI”, a fast neutron source reactor. The test foil used was 99.0% 107Ag enriched silver, which was irradiated along with five reference foils already well evaluated. The reaction rate of 107Ag was determined by K X-ray counting with a high-purity Ge detector. The cross section for the 107Ag(n, n′) 107mAg reaction was compiled from the excitation cross section data of 107Ag published in ENDF/B-IV, in combination with the decay scheme of 107mAg listed in the “Table of Isotopes“. Using the neutron spectrum which had previously been precisely measured, it was found that the compiled activity of 107mAg was underestimated by 12.8±5%. This error is attributed to significant underestimation involved in the cross section of the 107Ag(n, n′)107mAg reaction.
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