Verification and Analysis of the Problem-Dependent Multigroup Macroscopic Cross-Sections for Shielding Calculations

Xu Zhao, Shengchun Shi (), Wen Xu, Jiaju Hu, Jun Wu and Bin Zhang
Additional contact information
Xu Zhao: School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China
Shengchun Shi: Nuclear and Radiation Safety Center, Beijing 100082, China
Wen Xu: School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China
Jiaju Hu: Nuclear and Radiation Safety Center, Beijing 100082, China
Jun Wu: School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China
Bin Zhang: School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China

Energies, 2023, vol. 16, issue 8, 1-18

Abstract: Multigroup constants are the foundation of neutron and photon transport problems, and the accuracy of multigroup cross-sections has a significant impact on shielding calculation. Challenges have arisen in generating accurate multigroup macroscopic cross-sections for some problems using the widely used cross-section processing code TRANSX 2.15. We developed the multigroup neutron-photon macroscopic cross-section processing module in the shielding transport code ARES. The module is capable of handling the neutron-photon coupled master libraries in MATXS format and providing the problem-dependent multigroup macroscopic cross-sections tailored to each specific shielding physics problem. The self-designed problems with a single nuclide, as well as the iron and OKTAVIAN experiments, are used to verify and analyze the accuracy of neutron and photon macroscopic cross-sections. Results indicate that the macroscopic cross-sections, neutron flux and neutron-photon leakage spectrum obtained by the MGMXS module are consistent with corresponding reference values. As for the JANUS Phase I fixed source shielding benchmark, the relative differences in the reaction rate between the calculation results and experimental data are within 20%. The module provides better problem-dependent multigroup macroscopic cross-sections for neutron and photon shielding calculations that satisfy the accuracy requirements of engineering applications.

Keywords: shielding calculation; nuclear data library; MATXS format; multigroup cross-section (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2023
References: View complete reference list from CitEc
Citations:

Downloads: (external link)
https://www.mdpi.com/1996-1073/16/8/3366/pdf (application/pdf)
https://www.mdpi.com/1996-1073/16/8/3366/ (text/html)

Related works:
This item may be available elsewhere in EconPapers: Search for items with the same title.

Export reference: BibTeX RIS (EndNote, ProCite, RefMan) HTML/Text

Persistent link: https://EconPapers.repec.org/RePEc:gam:jeners:v:16:y:2023:i:8:p:3366-:d:1120783

Access Statistics for this article

Energies is currently edited by Ms. Agatha Cao

More articles in Energies from MDPI
Bibliographic data for series maintained by MDPI Indexing Manager ().