Cross-sections for , and reactions on molybdenum isotopes in the neutron energy range of 13 to 15 MeV *

Abstract

Given the insufficient cross-sectional data regarding the 14-MeV-neutron experiment of molybdenum, the vital fusion reactor structural material, and the significant heterogeneities among the reported values, this study examined the (n,2n), (n,α), (n,p), (n,d), and (n,t) reaction cross sections in molybdenum isotopes based on the neutrons produced via a T(d,n)4He reaction carried out in the Pd-300 Neutron Generator at the China Academy of Engineering Physics (CAEP). A high-resolution gamma-ray spectrometer, which was equipped with a coaxial high-purity germanium detector, was used to measure the product nuclear gamma activities. In addition, 27Al(n,α)24Na and 93Nb(n,2n)92mNb reactions were utilized as the neutron fluence standards. The experimental 92Mo(n,2n)91Mo, 94Mo(n,2n)93mMo, 100Mo(n,2n)99Mo, 98Mo(n,α)95Zr, 100Mo(n,α)97Zr, 92Mo(n,p)92mNb, 96Mo(n,p)96Nb, 97Mo(n,p)97Nb, 98Mo(n,p)98mNb, 92Mo(n,d)91mNb, and 92Mo(n,t)90Nb reaction cross sections were acquired within the 13–15 MeV neutron energy range. Thereafter, we compared and analyzed these obtained cross sections based on the existing IAEA-EXFOR database-derived experimental data, together with evaluation results corresponding to ENDF/B-VIII.0, JEFF-3.3, BROND-3.1, and CENDL-3.1 and the theoretical outcomes acquired through TALYS-1.95 and EMPIRE-3.2.3 (nuclear-reaction modeling tools).

Neutron-Induced Nuclear Cross-Sections Study for Plasma Facing Materials via Machine Learning: Molybdenum Isotopes

“…Gaussian process regression is a type of supervised learning algorithm that is based on Bayesian non-linear regression. The GPR algorithm is non-parametric, where probability distributions are surmised over all possible values of x. Theoretically, the data points can be represented as multivariate Gaussian [3,[17][18][19]. The neutron incident energy, E n is between 13 MeV to 17 MeV.…”

“…The machine learning model with R 2 closed to 1 and lowest RMSE is highlighted in yellow. [17,19] 133.6 −0.12 TALYS 1.9 + Borman et al [3,17] 133.6 −0.12 EMPIRE 3.2 + Borman et al [3,17] 133.6 −0.12…”

“…There are three main components to the input to feed into our algorithms, which are the incident energy of the neutron, E n , experimental cross-section data (EXP) and the computation cross-section, which consists of various output from EMPIRE 3.2 and TALYS 1.9 nuclear code done in the previous study [3,[16][17][18][19][20]. The output is the ENDF/B-VIII.0 library nuclear cross-section, and the list of inputs and outputs can be seen in Table 1.…”

“…The plasma-facing components are the first to be exposed to plasma generated from the D-T reaction in the reactor, which is heavily bombarded by fast neutrons (around 14 MeV). Thus, the materials used to fabricate plasma-facing components must be able to withstand the high neutron flux and are usually made from beryllium [1], tungsten [2], and molybdenum [3].…”

“…Figure 1. Graph of nuclear cross-section data of 92 Mo(n, 2N) 91 Mo nuclear reaction from various literature used in this work[3,[17][18][19]. The neutron incident energy, E n is between 13 MeV to 17 MeV.…”