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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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!
Latest Magazine Issues
Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
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.
Technical Session|Special Topics
Tuesday, August 22, 2023|1:30–3:10PM EDT|Gunston East/West
Session Chair:
Alessandro Del Nevo (ENEA)
Alternate Chair:
Megan Durse (Westinghouse Electric Co.)
Session Organizer:
Jun Liao (Westinghouse Electric Co.)
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GOTHIC Thermal Hydraulic Analysis of the Passive Heat Removal Facility to Support the Westinghouse Lead Fast Reactor Development
1:30–1:50PM EDT
M.E. Durse (Westinghouse Electric Co.), D.L. Wise (Westinghouse Electric Co.), J. Liao (Westinghouse Electric Co.), R.F. Wright (Westinghouse Electric Co.), C.A. Stansbury (Westinghouse Electric Co.), P. Ferroni (Westinghouse Electric Co.), M. Caramello (Ansaldo Nucleare), A. Wimshurst (Frazer-Nash Consultancy)
Paper
Numerical Analysis and Codes Qualification Based on SIRIO Experiments Within the PIACE Project
1:50–2:10PM EDT
P. Lorusso (ENEA), M. Tarantino (ENEA), F.S. Nitti (ENEA), A. Achilli (SIET), M. Cauzzi (SIET), M. Caramello (Ansaldo Nucleare), T. Hamidouche (SCK CEN), R. Fernandez (SCK CEN), D. Rozzia (SCK CEN), I. Kljenak (Jozef Stefan Institute), R. Krpan (Jozef Stefan Institute), G. Jimenez (Univ. Politécnica de Madrid), C. Queral (Univ. Politécnica de Madrid), T. Del Moro (Sapienza Univ. Rome)
Analysis of Steady State and Operational Transients of the Versatile Loop Facility in Support to Lead Fast Reactor Development
2:10–2:30PM EDT
C. Ciurluini (Sapienza Univ. Rome), M. Principato (Sapienza Univ. Rome), F. Giannetti (Sapienza Univ. Rome), M. Caramello (Ansaldo Nucleare), M. Tarantino (ENEA)
Application Development and Verification of Lead Cooling System Safety Analysis Program based on RELAP5 MOD4.0
2:30–2:50PM EDT
Xiangyang Wang (Lanzhou Univ.), Liu Yang (Lanzhou Univ.), Su Xingkang (Lanzhou Univ.), Qijian Chen (Lanzhou Univ.), Lu Zhang (Chinese Academy of Science), Xianwen Li (Chinese Academy of Science), Bin Han (Southeast Univ.), Aiguo Liu (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer), Bao-Wen Yang (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer), Gu Long (Lanzhou Univ.)
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