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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Latest News
Nuclear News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
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.
