Partial Cross-Section Calculations for PGNAA Based on a Deterministic Neutron Transport Solver
نویسندگان
چکیده
The measurement facility QUANTOM is being developed for the material analysis of radioactive waste packed up in 200-L drums. enables a spatially resolved elemental based on prompt gamma neutron activation analysis. evaluation spectra relies calculation partial (n,?) cross sections. Hereby, flux spectrum enters as parameter, which needs to be simulated full three-dimensional geometry facility. To ensure that simulations can carried out within an acceptable time frame, we use deterministic transport code specially this purpose SPN approximation linear Boltzmann equation. following question arises: Does model still allow sections at sufficient level accuracy. Therefore, paper, study light geometrical setting In simulation consider four typical matrix materials and compare all elements periodic table reference results obtained by Monte Carlo simulations.
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ژورنال
عنوان ژورنال: Nuclear Technology
سال: 2022
ISSN: ['0029-5450', '1943-7471']
DOI: https://doi.org/10.1080/00295450.2021.2016018