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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.
W. A. Coleman, R. G. Alsmiller, Jr.
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 104-113
Technical Paper | doi.org/10.13182/NSE68-A19536
Articles are hosted by Taylor and Francis Online.
Calculations are presented of the thermal-neutron flux as a function of position in a water moderator surrounding a variety of thick targets which are bombarded by protons in the energy range 540 to 2000 MeV. The calculated results are compared with experimental values, and very good agreement is obtained. Results are also given for the thermal-neutron flux as a function of position in a D2O moderator and for the energy deposition in the targets and the moderators.
