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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Science and Engineering
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Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
Kedar Bhope, Vinay Menon, Sunil Belsare, Samir Khirwadkar, Rajamannar Swamy, Mayur Mehta, Premjit Singh Kongkham, Tushar Patel, Nikunj Patel, Prakash Mokariya
Fusion Science and Technology | Volume 80 | Number 8 | November 2024 | Pages 931-940
Research Article | doi.org/10.1080/15361055.2023.2260536
Articles are hosted by Taylor and Francis Online.
The Institute for Plasma Research (IPR) is involved in the development of various technologies for fabrication and testing/qualification of tungsten (W)–based plasma-facing components for ITER-like applications. As a part of these activities, a small-scale W/Cu/CuCrZr monoblock test mock-up is prepared by using a vacuum brazing process. Further, thermal fatigue testing of this test mock-up is performed using the High Heat Flux Test Facility at IPR under an absorbed heat flux of ~9.5 MW/m2 for 1200 thermal cycles. Thermal-hydraulic analysis and computational fluid dynamics (CFD) simulations are also performed to understand the heat flux testing scenario. Nondestructive testing of the test mock-up after thermal cyclic heat flux testing indicates that there are no defects in the test mock-up except for minor cracks on the surface of W tiles. The results of thermal cyclic testing, finite element analysis, CFD analysis, and postanalysis of the High Heat Flux test are presented in the paper.