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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
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.