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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.
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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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.
V. O. Uotinen, J. H. Lauby, W. P. Stinson, S. R. Dwivedi
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 66-71
Technical Paper | doi.org/10.13182/NSE71-A18906
Articles are hosted by Taylor and Francis Online.
The ratio βeff/l has been deduced from reactor noise measurements in several uniform light-water lattices in the Plutonium Recycle Critical Facility. These lattices included one in which the fissile material was slightly enriched uranium, one in which the fissile material was plutonium, and five lattices in which the fissile material contained both uranium and plutonium. These measurements supply a set of experimental data over a range of plutonium enrichments that are applicable to plutonium recycle situations in thermal reactors. The measured values of βeff/l range from 33 ± 3 sec−1 for a lattice of Al-Pu rods to 153 ± 8 sec−1 for a lattice of UO2 rods. Calculated values of βeff/l, obtained with a straight-forward reactor design calculational method, are in good agreement with measured values.