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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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.