# Statistical Model Analysis of (n,p) Cross Sections and Average Energy For Fission Neutron Spectrum

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Recently measured energy dependences of fission cross sections of lead isotopes 204,206â€“208Pb at incident nucleon energies up to 180 MeV were analyzed. Regularities were established of the fission cross-section variation with the mass number of isotopes pointing to incomplete dumping of...

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Discrete Î³-ray spectra have been measured for nuclei populated in 191Ir(n,xnÎ³) reactions, with x â‰¤ 11, as a function of incident neutron energy using neutrons from the â€œwhiteâ€ neutron source at the Los Alamos Neutron Science Centerâ€™s WNR facility. The energy of the...

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The pseudo fission products for the burnup calculations of the liquid metal fast reactor were generated. The cross-section data and fission product yield data of ENDF/B-VI were used for the pseudo fission product data of U-235, U-238, Pu-239, Pu-240, Pu-241, and Pu-242. The pseudo fission...