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Comprehensive validation of silicon cross sections
Czakoj, Tomas,Kostal, Michal,Simon, Jan,Soltes, Jaroslav,Marecek, Martin,Capote, Roberto Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.12
Silicon, especially silicon in the form of SiO<sub>2</sub>, is a major component of rocks. Final spent fuel storages, which are being designed, are located in suitable rock formations in the Earth's crust. Reduction of the uncertainty of silicon neutron scattering and capture is needed; improved silicon evaluations have been recently produced by the ORNL/IAEA collaboration within the INDEN project. This paper deals with the nuclear data validation of that evaluation performed at the LR-0 reactor by means of critical experiments and measurement of reaction rates. Large amounts of silicon were used both as pure crystalline silicon and SiO<sub>2</sub> sand. The critical moderator level was measured for various core configurations. Reaction rates were determined in the largest core configuration. Simulations of the experimental setup were performed using the MCNP6.2 code. The obtained results show the improvement in silicon cross-sections in the INDEN evaluations compared to existing evaluations in major libraries. The new Thermal Scattering Law for SiO<sub>2</sub> published in ENDF/B-VIII.0 additionally reduces the discrepancy between calculation and experiments. However, an unphysical peak is visible in the neutron spectrum in SiO<sub>2</sub> obtained by calculation with the new Thermal Scattering Law.
Copper neutron transport libraries validation by means of a <sup>252</sup>Cf standard neutron source
Schulc, Martin,Kostal, Michal,Novak, Evzen,Simon, Jan Korean Nuclear Society 2021 Nuclear Engineering and Technology Vol.53 No.10
Copper is an important structural material in various nuclear energy applications, therefore the correct knowledge of copper cross sections is crucial. The presented paper deals with a validation of different copper transport libraries by means of activation of selected samples. An intense <sup>252</sup>Cf(sf) source with a reference neutron spectrum was used as a neutron source. After irradiation, the samples were measured using a high purity germanium detector and the dosimeter reaction rates were inferred. These experimental data were compared with MCNP6 calculations using CENDL-3.1, JENDL-4.0, ENDF/B-VII.1, ENDF/B-VIII.0, JEFF-3.2 and JEFF-3.3 evaluated Cu transport libraries. The experiment specifically focuses on <sup>58</sup>Ni(n,p)<sup>58</sup>Co, <sup>93</sup>Nb(n,2n)<sup>92m</sup>Nb, <sup>197</sup>Au(n,g)<sup>198</sup>Au and <sup>55</sup>Mn(n,g)<sup>56</sup>Mn dosimetry reactions. Evaluated activation cross sections of these dosimetric reactions were taken from the IRDFF-II library. The best library performance depends on the energy region of interest.