ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Karl Hornyik, Joseph A. Naser
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 36-49
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A16184
Articles are hosted by Taylor and Francis Online.
A model based on the RETRAN code was developed for analyzing the turbine trip tests performed at the Peach Bottom Atomic Power Station Unit 2, near the end of the second fuel cycle. Special features of the model include a detailed nodal description of the steam lines and the steam bypass system as needed to properly describe pressure wave phenomena caused by stop valve closure during the early phase of the transient, and dynamic effects associated with operation of the bypass. Furthermore, it is shown that the power excursion, deliberately enhanced by delayed scram, is strongly influenced by the nature of the pressure wave as it appears in the core region and by direct moderator heating effects. Good agreement between measured transients and most calculated counterparts makes this effort an important contribution toward qualification of RETRAN for this class of transients.