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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Latest News
Russia withdraws from 25-year-old weapons-grade plutonium agreement
Russia’s lower house of Parliament, the State Duma, approved a measure to withdraw from a 25-year-old agreement with the United States to cut back on the leftover plutonium from Cold War–era nuclear weapons.
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.