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Division Spotlight
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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Technology
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May 2025
Latest News
INL’s new innovation incubator could link start-ups with an industry sponsor
Idaho National Laboratory is looking for a sponsor to invest $5 million–$10 million in a privately funded innovation incubator to support seed-stage start-ups working in nuclear energy, integrated energy systems, cybersecurity, or advanced materials. For their investment, the sponsor gets access to what INL calls “a turnkey source of cutting-edge American innovation.” Not only are technologies supported by the program “substantially de-risked” by going through technical review and development at a national laboratory, but the arrangement “adds credibility, goodwill, and visibility to the private sector sponsor’s investments,” according to INL.
J. J. Hancke, G. T. Van Rooyen, J. P. R. De Villiers
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 49-56
Technical Paper | Fission Reactors/Fuel Cycle and Management | doi.org/10.13182/NT13-A15825
Articles are hosted by Taylor and Francis Online.
The crushing strength (load at fracture) of coated particles was measured by compression between soft metal anvils. The method requires no sample preparation and can be used as a quality control method as well as a valuable tool for comparing different coating conditions during the manufacture of TRISO particles. Batches of coated particles manufactured with different coating parameters were prepared and tested. Batches prepared under different conditions exhibited significant differences in crushing strength. Higher argon concentrations in the coater gas mixture resulted in higher crushing strength. Anomalies in the crushing strength of particles are related to defects and possibly residual stresses produced during coating. The influence of annealing at 1950°C on crushing strength was also investigated. The average crushing strength of batches of particles decreased with annealing. Different preparation methods showed a marked difference in the level of deterioration of the particles with annealing. Batches produced with 80% argon gas mixture at 1300°C showed the greatest reduction in crushing strength. An inverse correlation was found between the crushing strength and the uranium that is leached from batches. The particles with the lowest crushing strength would also be more susceptible to mechanical damage during handling and consequently also to leaching of the uranium during leach tests.