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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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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.
Cristian Contescu, Ann Campbell, Timothy Burchell, Nidia Gallego, A. L. Qualls (ORNL)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1168-1175
Since the successful completion of Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory, nuclear and material scientists continue to expand their knowledge on materials and conditions that would ensure safe and efficient operation of high temperature reactors with molten salt coolant. Carbon materials will be present in the reactor core as graphite moderators and reflectors in liquid-fuel molten salt reactor, MSR, and also as fuel matrix carbons in the fuel pebbles of thermal fluoride high temperature reactors (FHR). This paper summarizes the knowledge progress on carbon and graphite materials for molten-salt reactors starting from the lessons learned after the MSRE up to the newly revived interest for MSR in the last decade. Some unsolved items and knowledge gaps which require more research are emphasized.