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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
2020 ANS Virtual Winter Meeting
November 16–19, 2020
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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Missouri S&T’s nuclear engineering program gains department status
Missouri S&T’s pool-type nuclear reactor. Photo: Sam O’Keefe/Missouri S&T
Sixty years ago, the Missouri University of Science and Technology (Missouri S&T), then known as the University of Missouri at Rolla, was one of the first U.S. institutions to offer a nuclear engineering degree. Now, decades after it was offered as an option within metallurgical engineering, Missouri S&T’s nuclear program has attained new status as the Nuclear Engineering and Radiation Science Department, the university announced on October 20.
Technical Session|Sponsored by IRD
Tuesday, November 17, 2020|11:00AM–1:10PM (12:00–2:10PM EST)
The session will be available to join at 10:30AM (11:30AM EST).
Jeremy R. Licht
Akshay Dave (MIT)
Erik Wilson (ANL)
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Computational Software Developed by RERTR for the Conversion of Research and Test Reactors to LEU Fuel
Jeremy R. Licht (ANL), Arne P. Olson (ANL), Erik H. Wilson (Argonne National Laboratory)
Assessment of Reactor Kinetics Capability in RELAP5/MOD3.3 and PARET/ANL V7.6 to Support the Conversion of the University of Missouri Research Reactor to Low-Enriched Uranium Fuel
Dhongik S. Yoon (Argonne National Laboratory), J. A. Stillman (Argonne National Laboratory), E. H. Wilson (Argonne National Laboratory), E. E. Feldman (Argonne National Laboratory), K. Kutikkad (University of Missouri-Columbia Research Reactor), L. P. Foyto (University of Missouri-Columbia Research Reactor)
Formulas for Hot Channel Factors for Channels with Forced Flow
Jeremy R. Licht (Argonne National Laboratory), Mohammad Kalimullah (Argonne National Laboratory, Building 208, Room C150, Argonne, IL 60439), E. E. Feldmsan (Argonne National Laboratory, Argonne, IL 60439)
Thermal Analysis of Decay Heat Removal from a University of Missouri Research Reactor Discharged Low-Enriched Uranium Fuel Element
Dhongik S. Yoon (Argonne National Laboratory), John A. Stillman (Argonne National Laboratory), Earl E. Feldman (Argonne National Laboratory), Erik H. Wilson (Argonne National Laboratory), Wilson Cowherd (University of Missouri-Columbia Research Reactor), Les P. Foyto (University of Missouri-Columbia Research Reactor), Kiratadas Kutikkad (University of Missouri-Columbia Research Reactor), Nickie J. Peters (University of Missouri-Columbia Research Reactor)
Research and Test Reactor Fuel Modeling and Simulation with DART
Bei Ye (Argonne National Laboratory), Aaron Oaks (Argonne national laboratory)
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