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Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
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.