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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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December 2024
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November 2024
Latest News
Jeffrey King guides new nuclear program at Tennessee Tech
Jeffrey King
In August, the College of Engineering at Tennessee Technological University welcomed ANS member Jeffrey C. King as the founding director of its new nuclear engineering program. King, a leading force within the American Nuclear Society and a space enthusiast, is tasked with developing a new Department of Nuclear Engineering at Tennessee Tech after a more than 20-year absence of such a program at the university.
King comes to Tennessee Tech from the Colorado School of Mines, where he had been a professor of metallurgical and materials engineering for 15 years, leading the development of the nuclear science and engineering program and serving as director of the Nuclear Science and Engineering Research Center.
Nicolò Badodi, Antonio Cammi, Marica Eboli, Daniele Martelli, Alessandro Del Nevo
Nuclear Technology | Volume 209 | Number 10 | October 2023 | Pages 1508-1522
Research Article | doi.org/10.1080/00295450.2023.2188984
Articles are hosted by Taylor and Francis Online.
A major safety concern addressed during the design of the water-cooled lead-lithium (PbLi) breeding blanket (BB) is represented by an in-box loss-of-coolant accident, where high-pressure water is supposed to interact with PbLi inside the BB. Code development activities are being carried out to create the needed tools for the safety analysis of these systems in the case of incidental scenarios, which are supported by extensive experimental campaigns that aim at providing data for SIMMER code verification and validation (V&V). In this regard, the present work aims at presenting the dataset generated during the Series D experimental campaign performed at the LIFUS5/Mod3 facility operated at the ENEA Brasimone Research Centre. This is a separate effect facility able to simulate the mixing of water and PbLi alloy in conditions of temperature and pressure similar to the ones encountered by the system during nominal operation and to acquire significant data on all the relevant thermochemical parameters. Moreover, a preliminary analysis of the data has been performed to critically determine the quality of the data and to identify possible issues in the experimental process. In the end, the foreseen extension of the experimental work is described, as well as the foreseen application of the acquired data in the code V&V activities.