Calculation of accelerator-based neutron source anisotropy using SCALE6 system

This paper presents a developed definition of the accelerator-based neutron source that simulates neutron anisotropy of the tandem accelerator in SAV Piešt’any using the SCALE6 system developed by Oak Ridge National Laboratory. Anisotropy provides the yield and energetic distribution of the neutrons...

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Bibliographic Details
Main Authors: Kleštinec, Matej, Lűley, Jakub, Vrban, Branislav, Čerba, Štefan, Filová, Vendula, Nečas, Vladimír
Format: Conference Proceeding
Language:English
Subjects:
Anisotropy
Energy distribution
Mathematical analysis
Neutron radiography
Research facilities
Specifications
Online Access:Get full text
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Summary:This paper presents a developed definition of the accelerator-based neutron source that simulates neutron anisotropy of the tandem accelerator in SAV Piešt’any using the SCALE6 system developed by Oak Ridge National Laboratory. Anisotropy provides the yield and energetic distribution of the neutrons around a set direction. The developed neutron source definition incorporates specifications for the Tandetron’s energy distribution and directional distribution using precalculated theoretical values of anisotropy calculated by the DROSG-2000 program. The developed neutron source specification will find application in many fields, such as optimization of activities connected to the Tandetron, R&D activities, detector calibrations, safety calculations, neutron activation analyses, non-destructive neutron defectoscopy and neutron radiography.
ISSN:0094-243X
1551-7616
DOI:10.1063/5.0187479