journal article·1992-01

Impact behavior of reduced-activation ferritic steels irradiated in the Fast Flux Test Facility

R.L. Klueh, D.J. Alexander, P.J. Maziasz

Journal of Nuclear Materials· Volume 186· Issue 2
Publisher page

Abstract

No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.

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Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals

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References (15)

Show source-provided references
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7. Applications of Automation Technology to Fatigue and Fracture Testing
8. Klueh · J. Nucl. Mater. · 1991 · 179–181 · 67910.1016/0022-3115(91)90180-F ↗
9. Odette · 1985 · 840
10. Klueh · 1992
11. Hu · 1987 · 83
12. Fusion Reactor Materials Semiannual Progress Report
13. Gelles · 1990 · 113
14. Piet · Fusion Technol. · 1990 · 17 · 63610.13182/FST17-4-636 ↗
15. Klueh · J. Nucl. Mater. · 1991 · 179–181 · 72810.1016/0022-3115(91)90192-A ↗