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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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.
R. Bovalini, F. D’Auria, G. M. Galassi
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 89-111
Technical Paper | doi.org/10.13182/NSE93-A28521
Articles are hosted by Taylor and Francis Online.
A methodology is described that can be used for the extrapolation of thermal-hydraulic phenomena measured in differently scaled integral test facilities to nuclear reactor plant conditions. The use of a system code in this context is confirmed to be of fundamental importance, provided that the code’s scaling capability has been demonstrated. The starting data base for the proposed study consists of the measured quantities and corresponding RELAP5/MOD2 code calculation results related to a boiling water reactor small-break loss-of-coolant accident (SBLOCA) counterpart test activity, a pressurized water reactor (PWR) natural-circulation type test activity, and a PWR SBLOCA counterpart test activity. The proof that this methodology can be used for evaluating uncertainties in predicting transient behavior in nuclear power plants is the main result of this study. Data have been obtained that give a value of the foreseeable error ranges in the provision of plant behavior in the three cases considered.