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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
James P. Adams, Glenn E. McCreery, Jong H. Kim
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 325-340
Technical Paper | doi.org/10.13182/NSE91-A23858
Articles are hosted by Taylor and Francis Online.
An alternate pump trip criterion is described that meets the intent of the U.S. Nuclear Regulatory Commission pump trip requirement [i.e., to minimize primary system mass loss during a small-break loss-of-coolant accident (SBLOCA)] while providing the operators with a valuable tool to differentiate between various generic types of off-nominal transient conditions (heatup, cooldown, and loss-of-coolant accident) and to determine the efficacy of the recovery from these transients. The technique also provides a reliable measure of primary system mass inventory during heatup and cooldown transients and in the early phases of an SBLOCA. This method was developed by examining pump response to a variety of transients conducted in the Loss-of-Flow Test (LOFT) Facility. To explain the data, a mathematical model was developed based on one-dimensional pump theory. The response of the LOFT pumps was extended to full-scale commercial pressurized water reactor (PWR) pump response by examining general centrifugal pump behavior and by calculating PWR response to an SBLOCA. The results of the study indicate that the PWR pump behavior can be expected to be similar to that measured in LOFT and that the pump model can be used to gain valuable information on the status of a PWR during off-nominal transient conditions.