Reactor performance and safety characteristics of two-phase composite moderator concepts for modular high temperature gas cooled reactors

Duchnowski, Edward M.; Kile, Robert F.; Snead, Lance Lewis; Trelewicz, Jason R.; Brown, Nicholas R.

doi:10.1016/j.nucengdes.2020.110824

Cited by 13 publications

(1 citation statement)

References 24 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The Resource Team (RT) performed a systematic evaluation of eight cladding materials molybdenum, niobium, tantalum, FeCrAl, aluminum oxide [Al2O3], 8% yttria-stabilized zirconia [YSZ], SiC, and Inconel 690) in terms of the neutronic effect by using a hightemperature gas-cooled reactor (HTGR) model developed by Prof. N. Brown at University of Tennessee, Knoxville [15,16]. Each cladding was evaluated at different moderation levels to determine the optimal moderation.…”

Section: Reactor Physics Analysis Of Cladding Materials For Zirconium...mentioning

confidence: 99%

Downselection of Cladding Materials for Zirconium Hydride Moderator

Hiscox

Betzler

et al. 2021

View full text Add to dashboard Cite

This report complete Milestone M3.1.1 -"Cladding downselection: Team will report to ARPA-E on at least two down-selected cladding options-one metallic and one ceramic." In this milestone, we systematically assess FeCrAl alloys and SiC-based cladding options for a zirconium hydride (ZrHx) moderator in terms of their neutronics, radiation stability, hydrogen permeability, chemical compatibility, and fabricability. The analysis shows that FeCrAl alloys are excellent candidate cladding materials for a ZrHx moderator given their proven radiation stability, acceptable compatibility with ZrHx, and industrially established fabricability. The relative high hydrogen permeability is manageable by introducing a thin layer of an Al2O3 hydrogen permeation barrier on the external surface. The SiC-cladded ZrHx moderator is promising because of its outstanding neutronics performance, excellent radiation stability, and extremely low intrinsic hydrogen permeability. However, potential interactions of SiC and Zr and the challenge in achieving a hermetic SiC-based cladding require further investigation.

show abstract

Section: Reactor Physics Analysis Of Cladding Materials For Zirconium...mentioning

confidence: 99%