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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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ANS Congressional Fellowship applications due
Applications for the Society’s Glenn T. Seaborg Congressional Science and Engineering Fellowship will be closing soon. Congressional Fellows can directly contribute to the federal policymaking process, working in either a U.S. senator’s or representative’s personal office or with a congressional committee. They will be responsible for supplying Congress with their expertise in nuclear science and technology, having a hand in the creation of new laws while gaining a deeper understanding of the legislative process.
J. A. Turnbull, S. K. Yagnik, M. Hirai, D. M. Staicu, C. T. Walker
Nuclear Science and Engineering | Volume 179 | Number 4 | April 2015 | Pages 477-485
Technical Paper | doi.org/10.13182/NSE14-20
Articles are hosted by Taylor and Francis Online.
To investigate the potential disintegration to powder of high-burnup fuel pellets during a rapid temperature transient, the Nuclear Fuels Industry Research (NFIR) Program commissioned two independent scoping studies. The first investigated the effect of hydrostatic restraint pressure on fission gas release during a series of fast temperature ramps. In the second study laser heating was used to investigate the temperature at which small samples of fuel fragmented. From the observations made in these studies, local burnup and temperature thresholds of 71 MWd/kg HM and 645°C were identified for fuel pulverization during a loss-of-coolant accident (LOCA). It is shown that fine fragment production in integral LOCA tests performed in other independent investigations at Studsvik and Halden was generally well predicted using these thresholds of burnup and temperature. The NFIR investigations also reveal that the degree of pulverization and resulting fragment size are dependent on the temperature ramp rate. Moreover, they confirm that pulverization can be substantially reduced by the imposition of hydrostatic pressure.