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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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Latest News
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Mukesh Tayal, Ed Mischkot, Harve E. Sills, A. W. L. Segel
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 209-220
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT87-A33875
Articles are hosted by Taylor and Francis Online.
The ELOCA-A code models the thermomechanical behavior of CANDU fuel elements during high-temperature transients such as loss-of-coolant accidents. Calculations include sheath and pellet temperatures, strains (including creep), sheath oxidation, and beryllium-assisted cracking. The ELOCA-A code was developed by adding axial nodes to the ELOCA·MK2 code, which assumes axially uniform temperatures and strains. Thus, it is now possible to study the effects of axial variations such as end flux peaking, axial variations in the microstructure of Zircaloy due to brazing, axially nonuniform heat transfer, and axially nonuniform cross section due to the presence of appendages. Other features of ELOCA-A include choice of Urbanic-Heidrick or Baker-Just correlations for sheath oxidation and double-sided oxidation of a failed sheath. The ELOCA-A code shows reasonable agreement with axial variations in hoop strains measured at Chalk River Nuclear Laboratories. Calculations for some arbitrary transients confirm that axial variations in initial microstructure and in neutron flux can have a significant effect on fuel temperatures and strains.
