ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
W. S. Yeung, J. Shirkov, F. Seifaee
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 387-394
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A35021
Articles are hosted by Taylor and Francis Online.
The capability of the RELAP5/MOD3 computer code to analyze water hammer transients due to water column rejoining and a water slug propelled by non-condensable gas is investigated. The code-calculated results have been compared with those obtained from simple ideal analytical models. Good agreement is obtained between the calculation and analytical results in the initial period of the transient during which the water column or slug retains its sharp interface and suffers from little breakup or dissipation. As the transient proceeds, the code-calculated hydrodynamic loads are generally less than those implied by the analytical models. This is most likely due to the breakup of the water phase, which is not taken into account in the analytical models. Effects of time step and mesh sizes have also been studied. The results show that the usual Courant time limit applies. Finally, a sample calculation, corresponding to a water hammer transient in a typical Westinghouse four-loop reactor head vent system piping, is presented. The transient is induced by the opening of a relief valve and accelerating a trapped water slug through the pipeline. Hydrodynamic loads (i.e., force-time curves) on various pipe segments have been evaluated by appropriate postprocessing of the transient results. The calculated peak forces at selected pipe segments compare favorably with those estimated from the analytical models.