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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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August 2024
Latest News
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.
Victor E. Grob, E. Santandrea, Hilmar Ritz
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 514-524
Technical Paper | doi.org/10.13182/NSE60-A25760
Articles are hosted by Taylor and Francis Online.
As part of the Yankee and the Belgian Reactor-3 Critical Experiments program at the Westinghouse Reactor Evaluation Center, measurements have been made of the parameters leading to p, f, and ϵ in a light-water moderated heterogeneous reactor with slightly enriched UO2 fuel rods clad in stainless steel. A detailed description of this reactor is given in reference 1. Measurements were made using 4.48% and 2.73% enriched fuel with lattice pitches of 0.470 and 0.435 in. The individual UO2 sintered pellets, in the fuel rods, had a diameter of 0.300 in. and a length of 0.600 in. The 4.48% and 2.73% fuel rods contained 90 and 80 pellets, respectively. The stainless steel cladding was 0.305 in. i.d. and 0.347 in. o.d. for the 4.48% enriched fuel, and 0.306 in. i.d. and 0.338 in. o.d. in the case of 2.73% enrichment. The measurements were performed using a higher fuel enrichment than used previously at Bettis (2, 3) and elsewhere for similar experiments, thus uncovering a large unexplored range of enrichments.