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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.
P. B. Parks, N. P. Baumann, R. L. Currie, and C. E. Jewell
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 298-310
Technical Paper | doi.org/10.13182/NSE76-A26832
Articles are hosted by Taylor and Francis Online.
Experimental data that test the validity of a numerical solution of the transient few-group neutron diffusion and delayed precursor equations in two-dimensional hexagonal geometry are presented. The experiments involve free fall insertion of 235U-bearing rods into an off-center location of a large critical, heavy-water-moderated lattice. The resulting transient flux tilts are strongly influenced by delayed neutron holdback. The calculated flux tilts agree with the measured flux tilts within the small uncertainty of the measurements. The data and input to the calculations are presented in sufficient detail to allow other methods of solution to be tested.