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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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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.
Sandra M. Sloan, Yassin A. Hassan
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 177-182
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34344
Articles are hosted by Taylor and Francis Online.
The results generated from the IBM version of RELAP5/MOD2 are compared with the experimental data of an International Atomic Energy Agency standard problem exercise. The standard problem exercise data were that of a 7.4% break loss-of-coolant accident conducted at a test facility in Hungary. The United States did not formally participate in this exercise, whose aim was to assess the capabilities of computer codes and modeling techniques and in which a total of 17 organizations from 12 countries participated. The results obtained by execution of RELAP5/MOD2 on the IBM-3090 computer for upper plenum pressure, core inlet and outlet coolant temperature, and secondary-side pressure differed slightly during the latter part of the transient, but in general compared favorably to the experimental data. The magnitude of the cold-leg mass flow rate was underpredicted by the code.
