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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.
Yassin A. Hassan, Charles D. Morgan
Nuclear Technology | Volume 60 | Number 1 | January 1983 | Pages 143-150
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33110
Articles are hosted by Taylor and Francis Online.
Comparisons of the predictions of RELAP5/MODI to data obtained from a 19-tube model of a once-through steam generator (OTSG) were performed. The initial results were not satisfactory since the predicted outlet steam temperature was much too low. This discrepancy was traced to the inappropriate use of the modified Zuber critical heat flux (CHF) correlation for the conditions occurring during integral economizer OTSG operation. A study of available low-flow CHF correlations was performed that showed that either the Macbeth or Biasi correlations used in conjunction with RELAP5/MOD1 would produce good agreement with both the steady state and transient data for the integral economizertype OTSG. The Macbeth correlation was the best for the OTSG with a recirculation path; however, it was not entirely satisfactory due to a slight delay in its prediction of CHF A loss-of-feedwater transient was modeled using the Macbeth CHF correlation and compared to experimental data with satisfactory results.