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In this section, data S1 is utilized in simulation experiments.
We will address this issue in Section "Data compression".
The experiments were evaluated, peer reviewed, and analyzed with various codes and cross section data.
The model includes routines for interpolation of 2D section data and extrapolation for stall delay.
In the absence of cross section data, assumed or parameterized cross section shapes are often used.
Accuracy of the adjusted spectra was∼10% that was suitable for successive integral tests of activation cross section data.
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Based on the cross-section data, a mixing metric is computed for each cross section.
The simulations depend crucially on the scarce 33S n,α)30Si cross-section data.
The beryllium cross-section data were shown to be the main source of these uncertainties.
This cause the large number of cross-section data which must be stored and managed somehow.
The Monte Carlo transport code MCNP was used with the nuclear cross-section data library FENDL/2 offered by IAEA.
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