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Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Technical Session|Sponsored by THD
Wednesday, June 16, 2021|12:00–1:45PM EDT
Session Chair:
Robert P. Martin
Alternate Chair:
Dillon R. Shaver
Session Organizer:
Matthew D. Zimmer
Staff Producer:
Jessie Vazquez (ANS)
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Thermal Decomposition of Carbonates as a Passive Cooling Mechanism for Molten Salt Reactors
Christopher Forsyth (Univ. of California, Berkeley)
Paper
Study of Sodium Pool Fire Model Improvement in MELCOR for SFR
David L.Y. Louie (Sandia National Laboratories), Mitsuhiro Aoyagi (Japan Atomic Energy Agency)
Thermal Hydraulic Modeling of the Kairos Power Generic Fluoride High Temperature Reactor in MELCOR
Robert F. Kile (Univ. of Tennessee Knoxville), Friederike Bostelmann (ORNL), Steve E. Skutnik (ORNL), William A. Wieselquist (ORNL), Nicholas R. Brown (Univ. of Tennessee Knoxville)
Modeling of HTTF test PG-26 using RELAP5-3D and SAM
Aaron Epiney (INL), Thanh Hua (ANL), James Wolf (INL), Ling Zou (ANL), Gerhard Strydom (INL), Rui Hu (ANL)
Safety Assessment of Composite Alternative Moderators for Modular High Temperature Gas-Cooled Reactors
Veronica Karriem (Univ. of Tennessee Knoxville), Edward M. Duchnowski (Univ. of Tennessee Knoxville), Nicholas R. Brown (Univ. of Tennessee Knoxville)
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