ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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.
Meeting Spotlight
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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Ki-Yong Choi, Seok Cho, Hyoung-Kyu Cho, Chul-Hwa Song
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 54-67
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9445
Articles are hosted by Taylor and Francis Online.
The 6 × 6 reflood test facility for Advanced Thermal Hydraulic Evaluation of Reflood phenomena (ATHER) has been operated by Korea Atomic Energy Research Institute to investigate the reflooding phenomena in a rod bundle. A series of bottom reflood tests was carried out by varying several parameters affecting the reflooding process such as the flooding velocity, inlet coolant subcooling, system pressure, initial maximum rod wall temperature, and rod power. Subsequently, counterpart reflood tests of rod bundle heat transfer data from The Pennsylvania State University were conducted for comparison, focusing especially on the effects of the heat flux on the peak cladding temperature (PCT) and the quenching behavior. The best-estimate thermal-hydraulic system analysis code MARS3.1 was assessed with the obtained data to investigate the parametric effects on its prediction accuracy. It was found that the prediction accuracy of the PCT is reasonable on the whole but that the MARS code predicts delayed quenching behavior compared with the data, especially for high heat flux conditions. In particular, the prediction becomes deteriorated downstream, far from the inlet of the test section.
