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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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.
P. D. Krishnani, K. R. Srinivasan
Nuclear Science and Engineering | Volume 78 | Number 1 | May 1981 | Pages 97-103
Technical Note | doi.org/10.13182/NSE81-A19614
Articles are hosted by Taylor and Francis Online.
A method based on interface current formalism has been developed for solving the integral transport equation for cylindered pressurized heavy water reactor fuel lattices. In this a fuel cluster is divided into various rings, which are further subdivided into homogeneous zones like fuel, cladding, and associated coolant. The region outside the fuel cluster is also divided into a number of concentric annular (homogeneous) regions. A cosine current approximation is assumed at all the interfaces of the rings and annular regions while interactions between zones within a ring are directly calculated by the Pij method. In addition to this, the usual flat flux approximation is assumed for each of the homogeneous zones/regions. Based on this method, we have developed a one-group code, ANPROB, for calculating the flux distribution. The results obtained from the present method for 19- and 28-rod cluster lattices have been compared with the exact collision probability (Pij) method for clusters. It is found that the present method reduces the computational time considerably without sacrificing much of the accuracy.