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Use of Beryllium and Beryllium Oxide in Space Reactors

Journal Article · · AIP Conference Proceedings
DOI:https://doi.org/10.1063/1.1867196· OSTI ID:20630586
;  [1]
  1. Oak Ridge National Laboratory, P.O. Box 2008, OakRidge, TN 37831-6138 (United States)
Beryllium and beryllium oxide are attractive candidate materials for neutron reflector application in space reactors due to their beneficial combination of low density and high neutron moderation and reflection capabilities. Drawbacks to their use include the expense of working with toxic materials, a limited industrial infrastructure, and material properties that are challenging in the non-irradiated state and seriously degrade under neutron irradiation. As an example of neutron effects, mechanical properties degrade under relevant conditions to the point where encasement in structural alloys is necessary. Such measures are required if neutron fluence exceeds {approx}1x1024 n/m2 (E>0.1 MeV). At high temperatures (>500 deg. C for Be and >600 deg. C for BeO), irradiation-induced swelling may also limit the maximum allowable dose without additional engineering measures. Significant volumetric swelling (>5%) can occur in these materials during neutron irradiation at elevated temperatures for neutron fluences above 1x1025 n/m2. This paper will review Be and BeO fabrication considerations, and summarize the effects of neutron irradiation on material properties.
OSTI ID:
20630586
Journal Information:
AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 746; ISSN APCPCS; ISSN 0094-243X
Country of Publication:
United States
Language:
English