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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.
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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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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. Goldschmidt, J. Quenon
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 311-319
Technical Paper | doi.org/10.13182/NSE70-A19992
Articles are hosted by Taylor and Francis Online.
A method of optimizing the fissile fuel distribution to obtain minimum critical mass for a fast breeder reactor of fixed power is presented. Constraints on the power density and on the fuel enrichment are considered. The reactor is described by one-group diffusion theory. The optimal trajectory in the phase space (flux-current) is found a priori using the Maximum Principle of Pontryagin. It is shown that in general, the optimum reactor has three distinct regions: a central constant-power-density region, a region of maximum fuel enrichment and an outer region of minimum enrichment corresponding to the blanket. The existence of this last region and its dimension depend on the outer boundary condition which can simulate the presence of an external reflector. The expressions obtained for the optimized dimensions of each region can be solved analytically and numerical results are given.