Neutronics Analysis of Shielding Material Alternative to Tungsten Carbide in the FESS-FNSF Facility

Journal Article · 29 October 2024 · IEEE Transactions on Plasma Science

DOI: https://doi.org/10.1109/tps.2024.3477551 · OSTI ID:2475419

Rizk, Marina ^[1]; Brown, Nicholas R. ^[1]; Maldonado, G. Ivan ^[1]

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1. University of Tennessee, Knoxville, TN (United States)

Neutron transport calculations have been performed on advanced shielding materials. Metal hydrides and borohydrides were evaluated to find an alternative to tungsten carbide (WC), which is used in the in-vessel components. The study was conducted using a 22.5° sector and a detailed 360° geometry of the Fusion Energy System Studies-Fusion Nuclear Science Facility (FESS-FNSF) using OpenMC and FENDL-3.2b nuclear data library. Here, the neutronics analysis in this article was concentrated on calculating total nuclear (neutron and photon) heating at the magnet and the radiation damage of the inboard vacuum vessel (IBVV). For example, yttrium hydride (YH₂) and vanadium hydride (VH₂) showed lower radiation damage values compared to WC and other metals. Whereas alternative shielding materials did not show a significant change in the magnet nuclear heating.

• Research Organization: University of Tennessee, Knoxville, TN (United States)
• Sponsoring Organization: USDOE Office of Science (SC), Fusion Energy Sciences (FES)
• Grant/Contract Number: SC0022308
• OSTI ID: 2475419
• Journal Information: IEEE Transactions on Plasma Science, Journal Name: IEEE Transactions on Plasma Science Journal Issue: 9 Vol. 52; ISSN 0093-3813
• Publisher: IEEECopyright Statement
• Country of Publication: United States
• Language: English