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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Latest News
Crash Course: The DOE’s Package Performance Demonstration
Inspired by a history of similar testing endeavors and recommended by the National Academy of Sciences and the Blue Ribbon Commission on America’s Nuclear Future, the Department of Energy is planning to conduct physical demonstrations on rail-sized spent nuclear fuel transportation casks. As part of the project, called the Spent Nuclear Fuel Package Performance Demonstration (PPD), the DOE is considering a number of demonstrations based on regulatory tests and realistic transportation scenarios, including collisions, drops, exposure to fire, and immersion in water.
Peiwei Sun, Jin Jiang
Nuclear Technology | Volume 180 | Number 3 | December 2012 | Pages 399-421
Technical Paper | Special Issue on the Initial Release of MCNP6 / Thermal Hydraulics | doi.org/10.13182/NT12-A15352
Articles are hosted by Taylor and Francis Online.
In this paper, a dynamic model of the Canadian supercritical water-cooled reactor (SCWR) is developed to examine its dynamics for potential control system design and analysis. The model development is based on fundamental mass, energy, and momentum conservation equations of major components within the Canadian SCWR operating at supercritical condition. A full set of nonlinear dynamic equations is first derived, from which linearized models are obtained. The linearized models are validated against the full-order nonlinear models in both time domain and frequency domain. The open-loop dynamic characteristics of the Canadian SCWR are investigated through extensive simulations. Steady-state and dynamic couplings among different inputs and outputs are examined using relative gain array and Nyquist plots, and adequate input-output pairings are identified. Cross-coupling at different operating conditions is also evaluated to illustrate the nonlinear behaviors of the system. The developed dynamic model provides a necessary platform for systematic investigation in the control system design and analysis of the Canadian SCWR.