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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Neil D. Cox
Nuclear Science and Engineering | Volume 64 | Number 1 | September 1977 | Pages 258-265
Technical Paper | doi.org/10.13182/NSE77-A27096
Articles are hosted by Taylor and Francis Online.
A demonstration of two methods of uncertainty analysis was carried out to assess their utility for future use in treating computer models of nuclear power systems. The two methods of uncertainty analysis, called the response surface method and the crude Monte Carlo method, produced comparable results for the probability density function of the peak cladding temperature as computed by a simplified nuclear code that was subjected to seven uncertainty parameters. From these density functions, the upper cumulative tail probabilities were obtained and were shown to be measures of parameter margin. The response surface method provides sensitivity coefficients and also an inexpensive frame-work for evaluating the effects of the various assumptions inherent in the method. The crude Monte Carlo method provides no sensitivity coefficients and requires a complete rerun if a single uncertainty input density should be changed. The response surface method is recommended for use, where economically feasible, since the advantages of the method far outweigh the disadvantages.