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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Arvind Sundaram, Hany Abdel-Khalik
Nuclear Technology | Volume 207 | Number 8 | August 2021 | Pages 1163-1181
Technical Paper | doi.org/10.1080/00295450.2020.1812349
Articles are hosted by Taylor and Francis Online.
Can predictive models develop cognizance or awareness of how they have been used? Can models detect if they are being manipulated or executed in nonauthorized manners? Can a software track information propagation through its subroutines to improve execution efficiency? Can this be achieved in a covert manner, i.e., avoiding the use of additional variables, additional lines of code, and conventional logging files, and instead rely directly on the physics being simulated to develop the required cognizance? Achieving these goals under the looming threat of insiders is considered an open challenging problem. This paper introduces a new modeling paradigm to covertly develop cognizance that is of critical value when predictive software is used in both adversarial and nonadversarial settings. Given the wide range of applications possible with this new modeling paradigm, the paper will focus on introducing the mathematical theory and limit the initial demonstration to a physics-based model of a nuclear reactor. This model describes a representative industrial control system of a nuclear reactor model containing two coupled subsystems: a heat-producing core and a steam generator. The goal is to demonstrate how each subsystem physics model can remain cognizant of the state of the subsystem. The proposed methodology will provide communication solutions for future reactor technologies to enable advanced reactor control and remote reactor operations.