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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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.
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.