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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
W. R. Martin, J. R. Weir
Nuclear Technology | Volume 1 | Number 2 | April 1965 | Pages 160-167
Technical Paper | doi.org/10.13182/NT65-A20485
Articles are hosted by Taylor and Francis Online.
The tensile properties of Hastelloy N have been determined after irradiation at 700° C to a dose level of 7 × 1020 n/cm2 (E > 1 MeV) and 9 × 1020 n/cm2 (thermal). The strength and ductility of the material were determined as functions of deformation temperature for the range 20 to 900°C. These properties were also examined as functions of strain rate within the limits of 0.002 and 0.2 in./min (0.005 and 0.5 cm/min) for deformation temperatures of 500, 600, 700, and 800°C., The stress-strain relationship is not affected by irradiation at 700°C. Ductility, as measured by the true uniform and fracture strains, is reduced for deformation temperatures of 500°C and above. The loss in ductility results in a reduction in the true tensile strength. This loss is more significant at test conditions resulting in intergranular failure, such as low strain rates at elevated temperature. Postirradiation annealing of the irradiated alloy does not result in improved ductility. These data are compatible with the experiments suggesting helium generation from the (n,α) reaction of boron as the cause of low ductility., The low ductility of irradiated alloys in general is described in terms of the present knowledge of intergranular fracture. Means of improving the ductility are discussed.