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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Shih-Jen Wang, Chun-Sheng Chien, Jung-Yuh Jang
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 131-137
Technical Note | Reactor Operation | doi.org/10.13182/NT93-A34836
Articles are hosted by Taylor and Francis Online.
To apply fast and accurate simulation techniques to Taiwanese nuclear power plants, plant analyzer technology was transferred to Taiwan from the Brookhaven National Laboratory (BNL) through a cooperative program. The Chinshan plant analyzer was developed based on the BNL boiling water reactor plant analyzer. The simulation speed of the Chinshan plant analyzer is eight times faster than real time. The detail analysis process of the turbine trip transient is demonstrated. The self-initialization procedure automatically generates the desired plant conditions. These plant conditions are saved in a file and read directly for the simulation. The simulation is started by inputting the start time of the turbine trip from the keyboard of a personal computer. The simulation results are shown instantaneously on the screen of a Micro-VAX II workstation. A comparison of the calculated system response with the plant data indicates good agreement. The sequence of events is also close to that of the test result.