Abstract The article focuses on the validation of dosimetric neutron capture cross sections, namely 197Au(n,g)198Au, 63Cu(n,g)64Cu, 45Sc(n,g)46Sc, 59Co(n,g)60Co, 181Ta(n,g)182Ta, and dosimetric inelastic scattering cross section 204Pb(n,n')204mPb. The capture reactions were investigated within an epithermal neutron filter (boron carbide) in LR-0 zero power light water research reactor. . After the irradiation, the reaction rates were derived from the measured net peak areas of characteristic gamma rays. emissions. The IRDFF-II dosimetry library was chosen for validation using MCNP6.3 calculations. Notably, the spectrum-averaged cross section of 204Pb(n,n')204mPb in a 235U(nth,f) neutron field was measured for the first time, yielding an estimated value of (18.6 ± 3.2) mb. Concerning the capture reactions, comparison between experimental data and calculation employing IRDFF-II cross sections revealed discrepancies an all cases except for 197Au(n,g)198Au.
Schulc et al. (2026) studied this question.