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Division Spotlight
Fuel Cycle & Waste Management
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
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.
Stephane Cathalau, Amal Benslimane, Abdelmajid Maghnouj, Philippe Fougeras, Vladimir Ukraintsev
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 326-333
Technical Paper | doi.org/10.13182/NSE95-A28568
Articles are hosted by Taylor and Francis Online.
The calculation of reactor design parameters with ever higher accuracy requires constant improvement in basic nuclear data and computational techniques. Several methods based on formal statistical techniques have been studied to adjust cross sections used in fast reactor design calculations; nevertheless, these techniques have never been used for epithermal and thermal energy ranges. In this study, the statistical adjustment technique is reviewed, the integral experiments that serve as the adjustment database are presented, and suggested adjustments are discussed. If the cross sections of the main heavy nuclides seem to be well known, this study shows a very strong modification of the 235U capture cross section in the resonance range (∼10%). This trend can be explained by an underestimation of the mean capture width used in the 235U evaluation. The statistical technique used in this study allows us to qualify the JEF2 cross sections with a high quality of confidence.