Validation of deterministic code OpenNTP for the analysis of the C5G7-1D benchmark with different configurations. (September 2022)

• Record Type: Journal Article
• Authors: Lahdour, M.; El Bardouni, T.; El Hajjaji, O.; Chakir, E.; Boukhal, H.; Al Zain, Jamal; Makhloul, M.; Ziani, H.; El Yaakoubi, H.
• Is Part Of: Applied radiation and isotopes. Volume 187(2022)
• Publication Date: 2022-09
• Subjects: Multiplication factor -- Flux -- Power -- OpenNTP -- C5G7-1D; Radiology -- Periodicals; Radiation -- Industrial applications -- Periodicals; Nuclear chemistry -- Periodicals; Internet resource; Periodical; 660.298
• DOI: 10.1016/j.apradiso.2022.110317
• Languages: English
• ISSNs: 0969-8043

Abstract

Abstract: This study was conducted with the aim of verifying that the OpenNTP (Open Neutron Transport Package) code is capable of reproducing high-performance and exact calculation results. Therefore, a thorough analysis of the One-dimensional C5G7 benchmark with different configuration of control rods was performed. This benchmark was chosen because of its strong heterogeneity. For the modelling of the pin cell geometry, different sets of spatial meshes are used to study the sensitivity of the multiplication factors on the spatial and angular discretization. In addition, the influence of the control rods has been studied by analysing the scalar fluxes, the power in each pin cell and the power of the assemblies. It was found that assembly power distribution errors were significant for the Unrodded case of the C5G7 benchmark. The calculation results in the present paper have a good agreement with the reference values, which demonstrates that the OpenNTP code can solve neutronics problems accurately. Highlights: Validation of newly developed OpenNTP code. Analysis of the One-dimensional C5G7 benchmark with different configuration. Comparison between OpenNTP results and those of OpenMC code.