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Division Spotlight
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
Jorge V. Carvajal, Shawn C. Stafford, Michael D. Heibel, Paul M. Sirianni, Melissa M. Heagy, Robert W. Flammang, Nicola G. Arlia (Westinghouse), James A. Turso, Kenan Unlu (Penn State)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 246-257
This paper describes the development of radiation and temperature tolerant electronics capable of functioning inside an operating nuclear reactor vessel. The technology will enable every fuel assembly in a commercial reactor to be instrumented with self-powered neutron detectors (SPND) at different axial locations. Thermocouples for measuring the reactor coolant temperature may also be installed in every fuel assembly, as will an associated vacuum microelectronic (VME) wireless transmitter to continuously broadcast the signals from the SPND and/or thermocouples to a single receiving antenna inside the reactor vessel that will route the signal out of the reactor vessel. The successful development of this technology would enable key operating parameters of every fuel assembly in a commercial reactor core to be continuously monitored. The increase in reactor power distribution measurement density relative to existing densities, where roughly onethird of the fuel assemblies are instrumented, will significantly reduce the uncertainty in the measured core peaking factors. Reducing the uncertainty in the measured core peaking factors will allow the core operating power levels to be increased. This result will, in turn, allow the reactor to generate more electrical power from the same amount of fuel, operate at the same electrical output power level for longer periods before refueling with the same amount of fuel, or generate the same amount of electricity from less fuel.