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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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New coolants, new fuels: A new generation of university reactors
Here’s an easy way to make aging U.S. power reactors look relatively youthful: Compare them (average age: 43) with the nation’s university research reactors. The 25 operating today have been licensed for an average of about 58 years.
Robert L. Fish
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 85-95
Technical Paper | Material | doi.org/10.13182/NT76-A31701
Articles are hosted by Taylor and Francis Online.
The effects of two notch geometries on the tensile properties of fast-neutron-irradiated, annealed Type 304 stainless steel were investigated. Notch strengthening was observed under test conditions that promote transgranular failure accompanied by significant ductility (>5% total elongation) as measured using an unnotched specimen. These conditions existed at room temperature and moderate fluence levels (∼3 to 6 x 1022 n/cm2, E >0.1 MeV, ∼3 to 6 x 1026 n/m2, E >16 fJ). No notch effect was observed at 450 and 700°F (505 and 644 K) at any fluence level investigated. A notch weakening may exist under test conditions promoting low ductility (<1.5% total elongation) intergranular failure. At a nominal tensile strain rate (2.67 x 10-3/min, 4.45 x 10 -5/s), notch weakening was exhibited near 1100°F (866 K) and neutron fluences above 3 x 1022 n/cm2 (3 x 1026 n/m2). At a nominal strain rate, the notch sensitivity is independent of notch geometry between radii of 0.003 and 0.030 in. (0.076 and 0.76 mm). The notch sensitivity becomes notch geometry dependent at higher strain rates due to higher ductilities associated with a transition in the deformation and failure mode.