对 FESS-FNSF 设施中碳化钨屏蔽材料替代品的中子学分析

IF 1.3 4区物理与天体物理 Q3 PHYSICS, FLUIDS & PLASMAS

IEEE Transactions on Plasma Science Pub Date : 2024-10-29 DOI:10.1109/TPS.2024.3477551

Marina Rizk;Nicholas R. Brown;G. Ivan Maldonado

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

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. 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.

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来源期刊

IEEE Transactions on Plasma Science 物理-物理：流体与等离子体

CiteScore

3.00

自引率

20.00%

发文量

538

审稿时长

3.8 months

期刊介绍： The scope covers all aspects of the theory and application of plasma science. It includes the following areas: magnetohydrodynamics; thermionics and plasma diodes; basic plasma phenomena; gaseous electronics; microwave/plasma interaction; electron, ion, and plasma sources; space plasmas; intense electron and ion beams; laser-plasma interactions; plasma diagnostics; plasma chemistry and processing; solid-state plasmas; plasma heating; plasma for controlled fusion research; high energy density plasmas; industrial/commercial applications of plasma physics; plasma waves and instabilities; and high power microwave and submillimeter wave generation.