Thermal neutron scattering kernels for uranium mono-nitride: A potential advanced tolerant fuel candidate for light water reactors

Fluorinated borono‐phenylalanine for optimizing BNCT: Enhancing boron absorption against hydrogen scattering for thermal neutrons

“…The main reasons for such simplification is, in general, the lack of experimental and theoretical libraries describing the interaction of neutrons with large molecular systems, such as proteins in muscles or lipids in the brain. Moreover, the implementation of molecular-specific thermal cross sections based on analytic models or first-principles calculations [41][42][43][44][45][46][47][48][49] would inevitably cause additional computational costs in transport calculations. For this reason, phantoms used to evaluate dose rates are composed of well characterized materials, such as polymethylmethacrylate (PMMA), 50 for which thermal neutron libraries are well known.…”

Neutronic performance of 208Pb-Bi eutectic-cooled fast reactor with uranium nitride fuel (enriched 15N)

“…It is due to the UN fuel having several advantages, such as high melting point, high heavy metal density, and large thermal conductivity [19][20][21]. The use of UN fuel can also extend the fuel cycle in the core, resulting in lower electricity costs [22].…”

Thermal neutron cross sections of amino acids from average contributions of functional groups

“…Tabulated Thermal Cross Sections (TCS) are available for just a handful of systems [15][16][17] . In order to match the level of detail in modern Monte Carlo nuclear transport codes, the possibility to calculate TCS from simplified models 18 , from molecular dynamics 19 , as well as from ab initio calculations [20][21][22][23][24][25][26] has been a topic of recent development. Despite the important effort redirected into the theoretical calculation of TCS, the experimental data available for comparison and validation of the models is quite scarce.…”