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Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2024 ANS Winter Conference and Expo
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Orlando, FL|Renaissance Orlando at SeaWorld
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New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
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.