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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Wei-Jen Cheng, Robert S. Sellers, Mark H. Anderson, Kumar Sridharan, Chaur-Jeng Wang, Todd R. Allen
Nuclear Technology | Volume 183 | Number 2 | August 2013 | Pages 248-259
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT12-125
Articles are hosted by Taylor and Francis Online.
A corrosion test was performed on 316L stainless steel alloy (316L) and Hastelloy-N superalloy (Hastelloy-N) at 850°C for 1000 h in static molten fluoride salt, 46.5LiF-11.5NaF-42KF (mol %) with Zr additions. The interactions between the graphite sample and the tested alloys in the molten salt were also analyzed. The results show that Zr addition to the salt caused the deposition of a pure Zr coating on 316L and Hastelloy-N. The formation of this coating was followed by interdiffusion between the Zr deposit and the substrates. A thicker Zr deposit was observed on Hastelloy-N samples compared to 316L due to the larger electromotive potential difference between Ni/Zr than that between Fe/Zr. The interdiffusion subsequent to Zr deposition led to the formation of a coating composed of a Ni/Zr intermetallic phase even on the iron-based 316L. This intermetallic coating on the two alloys acted as a barrier layer for Fe and Cr outward diffusion. Zr3NiO and ZrO2 phases were also observed on the coating surfaces and in the coatings, respectively. The graphite sample, on the other hand, had no direct and significant effect on the corrosion behavior of the alloys and the coating formation on the alloys.