TL;DR
This paper identifies limitations in Geant4's neutron-HP package for thermal neutrons, proposes modifications, and develops a nuclear processing tool to enhance compatibility with evaluated nuclear data libraries, improving simulation accuracy.
Contribution
The paper introduces specific modifications to Geant4's neutron-HP package and a new nuclear processing tool to support additional data libraries, advancing neutronics simulation capabilities.
Findings
Improved agreement with reference code Tripoli for thermal neutron interactions.
Enhanced compatibility of Geant4 with ENDF-BVIII.0 and JEFF-3.3 libraries.
Validated modifications and tools for future Geant4 releases.
Abstract
An accurate description of interactions between thermal neutrons (below 4 eV) and materials is key to simulate the transport of neutrons in a wide range of applications such as criticality-safety, reactor physics, compact accelerator-driven neutron sources, radiological shielding or nuclear instrumentation, just to name a few. While the Monte Carlo transport code Geant4 was initially developed to simulate particle physics experiments, %-with a large emphasis given on modeled cross-sections for all known particles at all conceivable energies-, its use has spread to neutronics applications, requiring evaluated cross-sections for neutrons and gammas between and MeV (the so-called neutron High Precision -HP- package), as well as a proper offline or on-the-flight treatment of these cross-sections. In this paper we will point out limitations affecting Geant4 (version 10.07.p01)…
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