Evaluation of Neutron Cross Sections for a Complete Set of Nd Isotopes

Abstract

Neutron cross sections for a complete set of Nd isotopes, 142,143,144,145,146,147,148,150 Nd, were evaluated in the incident energy range from 10 −5 eV to 20 MeV. In the low energy region, including thermal and resolved resonances, our evaluations are based on the latest data published in the Atlas of Neutron Resonances. In the unresolved resonance region we performed additional evaluation by using the averages of the resolved resonances and adjusting them to the experimental data. In the fast neutron region, we used the nuclear reaction model code EMPIRE-2.19 validated against the experimental data. The results are compared to the existing nuclear data libraries, including ENDF/B-VI.8, JENDL-3.3 and JEFF-3.1, and to the available experimental data. The new evaluations are suitable for neutron transport calculations and they were adopted by the new evaluated nuclear data file of the United States, ENDF/B-VII.0, released in December 2006. 24.10.Eq, 24.60.Dr, 24.60.Gv, 25.40.Fq * Corresponding author.Email addresses: hikim@kaeri.re.kr (Hyeong Il Kim), mwherman@bnl.gov (M. Herman), mugabgab@bnl.gov (S. F. Mughabghab), oblozinsky@bnl.gov (P. Obložinský), rochman@nrg-nl.com, present address NRG, PO Box 25, 1755 ZG Petten, The Netherlands (D. Rochman), yolee@kaeri.re.kr (Young-Ouk Lee).

Calculations of (n,2n) reaction cross sections for Barium isotopes from 5 to 20 MeV

“…Importance of theoretical cross-section calculations for fast fission and fusion reactors increase in recent years. Fission products accumulate in an operating reactor as the fuel undergoes fission [5]. Cross sections for (n,2n) reactions induced by neutrons of 14-15 MeV energies have been calculated by many researches covering all the elements of the periodic table.…”