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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
Dong H. Nguyen
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 61-74
Technical Paper | Safety of Next Generation Power Reactor / Fission Reactor | doi.org/10.13182/NT90-A34441
Articles are hosted by Taylor and Francis Online.
The design of the next generation of power reactors will emphasize passive safety and enhanced engineered systems. True passivity can be achieved by capitalizing on natural laws to restore reactor stability during an off-normal event. The most effective stabilizing mechanisms relying solely on natural laws— without human interference—are the feedback reactivities produced by a change in the reactor thermal state. During 1986 and 1987, an important research program was undertaken at the Fast Flux Test Facility (FFTF) to advance the understanding of feedback mechanisms and to investigate passive safety in liquid-metal reactors. The experimental program began with a series of static feedback reactivity measurements aimed at separating feedback components and ended with a demonstration of passive safety in a series of loss-of-flow-without-scram (LOFWOS) to natural circulation tests. Described here are (a) the fundamental experimental concepts used to unfold various feedback components, (b) the analysis of integral data used to construct feedback reactivity models, (c) the comparison of FFTF reactivities with mechanistic feedback models in the SASSYS/SAS4A code system, and (d) the pretest calculations for the LOFWOS test series, using the new FFTF feedback models.