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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Peter J. Jensen, James F. Lang, Jason Chao
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 279-289
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33881
Articles are hosted by Taylor and Francis Online.
A method allowing individual representation of a ruptured steam generator tube without including it explicitly in the RETRAN-02 nodalization was investigated. The resulting methodology allows accurate representation of flow through a single ruptured tube without incurring prohibitive computing costs. The study considered a wide variety of fluid conditions at the rupture ranging from subcooled liquid to two-phase fluid and from choked to unchoked rupture flow. Although only one tube rupture geometry was considered, this study provides the groundwork from which methods specific to other geometries can be easily developed. Portions of this method were compared with RELAP5 calculations and good agreement was shown. This methodology was incorporated in a RETRAN-03 analysis of a steam generator tube rupture event in a Westinghouse two-loop plant. This included a case with a tube rupture accompanied by loss of off-site power as well as a case incorporating procedures for operator actions during a tube rupture event. The results indicate both the impact and the necessity of appropriate operator actions in such an event. The RETRAN-03 computer code was found to perform satisfactorily when this tube rupture modeling technique was incorporated. Faster than “realtime” computational speed was demonstrated on a Cyber 176 computer when using a fairly detailed RETRAN plant model (54 volumes, 82 junctions).