ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
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.
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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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.
Thomas M. Parker, Richard J. Kohrt, Sue I. Dederer, Larry E. Hochreiter, Walter R. Schwarz, Chon-Kwo Tsai, Michael Y. Young
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 227-237
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34243
Articles are hosted by Taylor and Francis Online.
Calculations were performed using a best-estimate computer code that determined the estimates of the 50th percentile peak cladding temperature (PCT) (1006 K) and the 95th percentile PCT (1263 K). These calculations included realistic WCOBRA/TRAC predictions of thermal-hydraulic phenomena occurring inside the vessel during upper plenum injection (UPI). The work done in applying realistic thermal-hydraulic methods for pressurized water reactors (PWRs) with UPI represents an important step in the maturation of advanced best-estimate computer codes like WCOBRA/ TRAC because their effect is finally being used in the licensing of operating plants, and their benefits are being used to make those PWRs more flexible and economic to operate.
