Fission Yields and Other Diagnostics for Nuclear Performance

Gadolinium for neutron detection in current nuclear instrumentation research: A review

“…A number of nuclear data libraries are available in addition to the MCNP6 code so that the gamma-ray RP of 157 Gd (n,γ) and 155 Gd (n,γ) reactions may be generated. The ENDF/B-VII.0 library is notably used to generate the prompt electromagnetic source term after neutron capture [36]. To obtain a representation of the photon spectrum generated by the library, a simple configuration was simulated: a neutron source with energy E n = 25 meV was positioned at the center of a natural Gd ball, with isotopic composition from Table 2, density ρ = 7.901 g. cm -3 , and radius r = 10 µm.…”

Radiation transport calculations for the European Spallation Source accelerator environment

“…The default nuclear cascade model in MCNP6.2 is the Cascade-Exciton model (CEM) [17,18,19]. Generally, proton and neutron libraries were taken from ENDF/B-VII.0/VII.1/VIII [20,21,22] but in some limited cases we supplemented the above libraries with data from TENDL-2017/2019 [23,24], JENDL-4.0 [25] and JEFF 3.2 [26].…”

Basic concept for an accelerator-driven subcritical system to be used as a long-pulse neutron source for Condensed Matter research

“…The required nuclear data is taken from ENDF-VII.0 [24] crosssection libraries. Thermal scattering libraries are used to compute the cross-section of atoms bound to a molecule at different temperatures.…”