Compendium of benchmark neutron fields for reactor dosimetry :

Use of Neutron Benchmark Fields for the Validation of Dosimetry Cross Sections

“…In Fig. 3b the C/E ratios were computed using the JENDL 4.0 235 U thermal fission neutron spectrum [8], the Grundl measurements [4], and the IRDFF cross sections [1]. The 47 Ti(n,p) reaction discrepant C/E [7] in the original data is again seen to be fixed with the latest cross sections.…”

“…The other three reactions with a low energy median response energy [ 6 Li(n,d), 10 B(n, ), and 197 Au(n, )] have a much smaller overall uncertainty but show significant deviations from unity. These measurements come from the NBS measurements [4]. The 10 B(n, ) and 6 Li(n,d) reactions are discussed in more detail in Sect.…”

“…Historically, when comparisons with integral benchmarks have been made, rather than reporting a spectrum-averaged cross section, the analyst has used, as the metric of interest, a spectral index (SI) [4]. A spectral index is the ratio of the spectral-averaged cross section for two different reactions, a detector and a reference reaction, gathered in a neutron field for the same exact irradiation.…”

“…In Fig. 2b the C/E ratios were computed using the Mannhart 252 Cf spontaneous fission neutron spectrum [6], the Grundl measurements [4], and the IRDFF cross sections [1]. The discrepant outlier in Fig.…”

“…Reference 10 shows that when the 10 B(n,t2 ) reaction is added into the analysis, the C/E for the 10 B(n, ) analysis is ∼1.0. Similarly, when the 6 Li(n,nd ) and 6 Li(n,2np ) reactions are included in the analysis, the 6 Li(n,t) 4 He reaction gives a C/E of ∼1.03. The original NBS measurements for 10 B and 6 Li were labelled as "helium production" reactions and obviously addressed the composite reaction and thus should be treated as 10 B(n,X) 4 He and 6 Li(n,X) 4 He reactions.…”