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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
Jun Wang (Univ of Wisconsin, Madison), Anil Gurgen (MIT), Michael L. Corradini (Univ of Wisconsin, Madison), Koroush Shirvan (MIT)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 755-762
In order to compare the thermal hydraulics system response to Accident Tolerant Fuel (ATF) materials, a benchmark was performed for early accident progression behavior given a Station Blackout scenario. Thermal hydraulic parameters such as the pressurizer pressure, reactor pressure vessel (RPV) water level, peak cladding temperature, and hydrogen mass generated were quantified by the TRACE code by a team at MIT and compared to MELCOR by a team at UW Madison. This benchmark comparison with TRACE and MELCOR used the same initial conditions for a simplified generic PWR plant model. This PWR model was based on a 2200MWth conventional light water reactor plant. The benchmark work included the input model development and the simulation comparisons for the thermal hydraulic response, pressurizer relief valve operation, and the clad oxidation. The Zircaloy cladding case and FeCrAl cladding case were compared in the current simulation. The result showed good agreement between TRACE and MELCOR for overall event timing and key parameters. The exothermic energy release from Zircaloy and FeCrAl clad oxidation were calculated and compared. The difference in oxidation energy between the clad materials was quite small when compared to decay heat values.