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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.
A. Rotenberg, A. Lapidus, E. Wetherwell
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 288-293
Technical Paper | doi.org/10.13182/NSE59-A28846
Articles are hosted by Taylor and Francis Online.
A Monte Carlo calculation of thermal utilization is described with emphasis on the statistical procedures employed. The reactor model has slightly enriched uranium fuel rods in a hexagonal lattice. The moderator is ordinary water but is treated by the code as a hydrogen gas. General principles are given for using Monte Carlo techniques and it is shown that time reducing methods are as effective as the better known variance reducing methods in decreasing the cost. Good agreement with experimental results was obtained, indicating that such thermal utilization calculations are feasible and are not sensitive to the model of the water molecule.