Accuracy Evaluation of Monte Carlo Simulation Results Using ENDF/B-VIII.0 and JENDL-5 Libraries for 10 MW_th Micro Heat Pipe-Cooled Reactor

Figure 8

Covariance matrices of ²³⁵U total ν, ²³⁵U fission, ²³⁸U, ²³⁵U, ¹⁶O, and ⁵⁶Fe capture cross sections of ENDF/B-VIII.0 and JENDL-5 libraries. (a) Covariance matrices of ²³⁵U total ν, ²³⁵U fission and ²³⁸U capture cross sections, and (b) Covariance matrices of ²³⁵U, ¹⁶O, and ⁵⁶Fe capture cross sections.

(a)

(b)