Development and potential of composite moderators for elevated temperature nuclear applications. Issue 1 (2nd January 2022)

• Record Type: Journal Article
• Authors: Snead, Lance L; Sprouster, David; Cheng, Bin; Brown, Nick; Ang, Caen; Duchnowski, Edward M; Hu, Xunxiang; Trelewicz, Jason
• Is Part Of: Journal of Asian ceramic societies. Volume 10:Issue 1(2022)
• Page Start: 9
• Page End: 32
• Publication Date: 2022-01-02
• Subjects: Neutron moderator -- reactor -- composite -- irradiation -- magnesia -- beryllium -- zirconium-hydride; Ceramics -- East Asia -- Periodicals; Materials science -- Periodicals; 620.1405
• DOI: 10.1080/21870764.2021.1993592
• Languages: English
• ISSNs: 2187-0764

Abstract

ABSTRACT: Neutron moderators, such as nuclear-grade graphite, are essential components of high-temperature nuclear reactors. Their primary functions are to degrade the energy of fission-born neutrons into an energy range that promotes further fission and to serve as the central core structure. This paper will discuss historic reactor moderator materials, which are relatively simple monolithic materials each having intrinsic benefits and limitations. Additionally, a new class of engineered composite moderators is presented for which two examples are fabricated: magnesia-matrix composite systems with either beryllium-based or metal-hydride entrained phases. In additions to presenting their route to fabrication effectiveness as advanced moderators is discussed.