Development and potential of composite moderators for elevated temperature nuclear applications

Snead, Lance Lewis; Sprouster, David; Cheng, Bin; Brown, Nicholas R.; Ang, Caen; Duchnowski, Edward M.; Hu, Xunxiang; Trelewicz, Jason R.

doi:10.1080/21870764.2021.1993592

Cited by 17 publications

(1 citation statement)

References 85 publications

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“…In our previous work (Cheng et al, 2022;Snead et al, 2022;, composite sintering temperature was significantly suppressed through the use of LiF sintering aid in the monolithic MgO and MgO (LiF): ZrH 2 systems. This initial 350 °C reduction in MgO sintering temperature, and the 250 °C increased processing temperature for ZrH 2 through processing in a hydrogen atmosphere allowed the first demonstration of a ceramic-matrix metal-hydride composite.…”

Section: Frontiers In Nuclear Engineeringmentioning

confidence: 99%

Fabrication of neutron absorbing metal hydride entrained ceramic matrix shield composites

Bhardwaj,

Cheng,

Sprouster

et al. 2024

Front. Nucl. Eng.

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With significant improvement in High Temperature Superconductors (HTS), several projects are adopting HTS technology for fusion power systems. Compact HTS tokamaks offer potential advantages including lower plant costs, enhanced plasma control, and ultimately lower cost of electricity. However, as compact reactors have a reduced radial build to accommodate shielding, HTS degradation due to radiation damage or heating is a significant and potentially design limiting issue. Shielding must mitigate threats to the superconducting coils: neutron cascade damage, heat deposition and potentially organic insulator damage due x-rays. Unfortunately, there are currently no hi-performance shielding materials to enable the potential performance enhancement offered by HTS. In this work, we present a manufacturing method to fabricate a new class of composite shields that are high performance, high operating temperature, and simultaneously neutron absorbing and neutron moderating. The composite design consists of an entrained metal-hydride phase within a radiation stable MgO ceramic host matrix. We discuss the fabrication, characterization, and thermophysical performance data for a series of down-selected composite materials inspired by future fusion core designs and their operational performance metrics. To our knowledge these materials represent the first ceramic composite shield materials containing significant metal hydrides.

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Section: Frontiers In Nuclear Engineeringmentioning

confidence: 99%