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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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February 2025
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January 2025
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Latest News
US, Korea sign MOU for nuclear cooperation
The U.S. departments of Energy and State have signed a memorandum of understanding with the Republic of Korea’s ministries of Trade, Industry and Energy and of Foreign Affairs for the two nations to partner on nuclear exports and cooperation.
Alexander Duenas, Daniel Wachs, Guillaume Mignot, Jose N. Reyes, Qiao Wu, Wade Marcum
Nuclear Science and Engineering | Volume 196 | Number 2 | February 2022 | Pages 193-208
Technical Paper | doi.org/10.1080/00295639.2021.1955591
Articles are hosted by Taylor and Francis Online.
New fuel design and development currently require 20 to 25 years to be qualified for use by the nuclear power industry. The thermal-hydraulics community has taken advantage of scaling theory to design reduced-scale experiments that correctly preserve dominant key phenomena while quantifying distorted phenomena. These techniques can be leveraged in the design and analysis of fuel performance experiments to help reduce the timeline associated with fuel design and development. This study uses the Dynamical System Scaling (DSS) method to analyze cladding temperature data from the recent SETH-C experiment in the Transient Reactor Test Facility (TREAT) and accompanying BISON simulations to assess dynamic distortions occurring throughout the fast power excursion transient. The DSS analysis revealed that on the cooldown from peak cladding temperature, the fuel radial power profile is the most sensitive modeling parameter, with a heterogeneous radial peaking factor corresponding to the lowest distortion compared to a uniform energy deposition. For the heatup to PCT, the heterogeneous radial power profile corresponded to the shortest process action. Last, for the heatup to PCT, the gap conductance model sensitivity was quantified using process actionsm and showed that the default light water reactor gap conductance model corresponded to the longest process action.