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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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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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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Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
Vikram Singh, Alexander M. Wheeler, Belle R. Upadhyaya, Ond?ej Chvá (Univ of Tennessee, Knoxville), M. Scott Greenwood (ORNL)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 199-208
Preliminary results from a nonlinear dynamic model of the Molten Salt Demonstration Reactor (MSDR) plant are presented. This model is coupled to an integral economizer Once-Through Steam Generator (OTSG) model with variable boiling length to simulate operation at different power levels. The reactivity effect of Xe-135 is also integrated to investigate open-loop load-following operation. Simulation results show that the reactor model is stable for the investigated reactivity perturbations. A load-following excursion is simulated by varying the feedwater flow rate through the steam generator. Results show that the MSDR can follow load demand in a stable manner through temperature-based reactivity feedbacks alone without requiring operator input. Future work involves development of instrumentation systems and control strategies to achieve near autonomous plant operation.
