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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
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.