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
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
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Latest News
The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
Seong-Su Jeon, Soon-Joon Hong, Hyoung-Kyu Cho, Goon-Cherl Park
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 303-318
Technical Paper | doi.org/10.13182/NT16-22
Articles are hosted by Taylor and Francis Online.
A horizontal U-shaped heat exchanger (HX) submerged in a pool is under development as a piece of key equipment for a passive safety system in a nuclear power plant (NPP). For the successful design of the HX and the safety analysis of the NPP, reliable prediction of the heat transfer performance of the HX is important. At present, the design and the safety analysis of the passive safety systems are performed mainly using best-estimate thermal-hydraulic analysis codes such as RELAP5 and MARS. However, those codes do not have suitable models for both condensation heat transfer in the horizontal tube and natural convective and nucleate boiling heat transfer on the horizontal tube, both of which ultimately determine the heat transfer performance of the HX. This study developed a heat transfer model package for the horizontal U-shaped HX submerged in a pool by improving the horizontal in-tube condensation model and developing the out-tube natural convective and nucleate boiling model. From the validation results, the proposed model provides an improved prediction of HX performance (condensation, natural convection and nucleate boiling, and heat removal rate of the HX) compared to the default model in MARS.