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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.
Yao W. Chang, Joseph Gvildys
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 388-399
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32575
Articles are hosted by Taylor and Francis Online.
Primary containment computer codes, REXCOHEP (Lagrangian), ICECO (Eulerian), ALICE (ALE), and REXALE (ALE), developed in the Engineering Mechanics Program of Argonne National Laboratory, were validated by performing comparison with the analytical solution and experimental data. Three problems were used. The first problem deals with the propagation of shock wave in a rigid tube for which analytical solution exists. The second problem concerns the response of a simple flexible vessel to a hypothetical core disruptive accident (HCDA)-in-duced pressure loading for which experimental data exist. The experiment was performed with a well-defined and calibrated energy source. It provided reliable test data for code validation. The third problem concerns the propagation of shock wave in a three-dimensional space for which the experimental data exist. Results of the comparisons show that the Lagrangian, Eulerian, and ALE codes can all give acceptable solutions to the shock wave propagations and on the response of containment vessel to HCDA-induced pressure loading.