ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Apr 2025
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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.
Nick DeJulia, Trevor Jones (AMS)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 1251-1259
A pressurized water reactor (PWR) is equipped with a magnetically coupled positioning system known as a control rod drive mechanism (CRDM). In many cases, the plant system that measures the position of the control rods in the reactor core is the digital rod position indication (DRPI) system. The DRPI system is designed to continuously sense and display the positions of each of the control and shutdown rods. Both of these systems consist of coils above the reactor head, connectors at the reactor head and at the containment penetration, instrumentation and power cabinets, and long runs of interconnecting cables in between these system components. The objective of cable testing is to evaluate the condition of the rod control and position indication coils, connections, cables and to identify any defects or anomalies that may adversely affect their normal operation. Various electrical measurements can provide insight into the health and reliability of these rod control and rod position cable circuits. Some measurements are used to identify configuration anomalies, others test the integrity of connectors and proper isolation from station ground, and some validate the health of the coil to identify resistive connections, insulation degradation, or turn-to-turn shorts. This systematic approach to rod control and rod position coil and cable testing increases system reliability, reduces the likelihood of unplanned outages from dropped rods, and reduces outage times and maintenance costs which in turn reduces costs for the electrical utility.