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
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Jong-Won Kim, Jong-Soo Choi, Young-In Kim, Young-Jong Chung, Goon-Cherl Park
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 336-351
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13479
Articles are hosted by Taylor and Francis Online.
SMART (System-integrated Modular Advanced ReacTor) is an integral-type nuclear reactor for cogeneration that adopts a flow mixing header assembly (FMHA) to maintain a uniform temperature distribution in the coolant at the core inlet in the case of failure in the steam generator or reactor coolant pump. The SMART FMHA is important for enhancing thermal mixing of the coolant during a transient and even during accidents, so it is essential that the thermal-hydraulic characteristics of flow in the FMHA be understood. Scaling analysis was performed to design the experimental facility for the FMHA test through computational fluid dynamics (CFD) analysis on the SMART prototype and experimental model. The experimental facility was designed by a linear scaling factor 0.18, and the experimental pressure and temperature conditions were 0.1 MPa and 30°C to 60°C, respectively.The experiment was performed in two ways: using FMHAs with large outlet flow hole sizes and FMHAs with small outlet flow hole sizes. In the cases of failure of one or two steam generators, the maximum temperature deviation on the side of the reactor core inlet was measured to be 1°C to 2°C, which demonstrates excellent thermal mixing through the FMHA. In particular, the FMHA with small outlet flow hole sizes tended to have better thermal mixing than the FMHA with large outlet flow hole sizes. The experimental results were comparable to those from CFD analysis.