Thermal Neutron Crosssections in Geant v11.3

Physics Processes, Models and Cross Sections
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Geant4 Version: 11.3.2
Operating System: AlmaLinux 9.8
Compiler/Version: GCC version 11.5.0
CMake Version: 3.31.8

Hi everybody. I am wondering what the correct way to treat thermal neutrons within Geant4. The physics list I am using is QSP_BIC_HPT. To my Knowledge the treatment of thermal neutrons has changed in recent years. Is it sufficient to register materials via NIST, or do I need to register each element with the adequate naming schemes. If that is the case, I would appreciate some information on what the current naming scheme looks like, since previous attempts of mine to include thermal crosssections that way failed.

Thanks in advance for your help!

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Hi, you can download CS from GEANT 4 Libraries , follow the instruction in readme, then export them via export G4NEUTRONHPDATA=$GEANT4_DATA_DIR/JEFF-4.0. For example JEFF-4.0 (probably the most actual). Or download G4TENDL1.4 from Download Geant4-11.4.2 - Geant4 and do export G4PARTICLEHPDATA=$GEANT4_DATA_DIR/G4TENDL1.4. The you can use QGSP_BIC_AllHP.