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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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, Shih-Hsiin Chang, Ling-Yao Chou
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 280-290
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35208
Articles are hosted by Taylor and Francis Online.
An anticipated transient without scram induced by main steam isolation valve closure (AMSIV) could subject a nuclear power plant to the most severe of accident conditions. The Chinshan plant analyzer contains a complete boiling water reactor system model and can be revised easily for the user’s purpose. These features make the Chinshan plant analyzer suitable for AMSIV analysis. The capability of the Chinshan plant analyzer to analyze an AMSIV is illustrated. An AMSIV is simulated, and the simulation results are similar to the results of other research. Furthermore, the AMSIV response of reducing reactor power by decreasing reactor coolant inventory is simulated, and the results of the simulation are similar to those of other research. During this transient, the reactor power is decreased. However, the margin to core uncovery is also decreased. In addition, a method of reducing the reactor power by increasing the feedwater temperature is studied. The mechanism of reducing the reactor power is associated with decreasing the inlet subcooling. Sensitivities of key parameters are also analyzed. A large negative void coefficient causes an undesirable large peak in the reactor power. A small recirculation pump moment of inertia decreases the reactor power.
