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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.
Koichi Sekimizu, Kazuo Monta
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 474-481
Technical Note | doi.org/10.13182/NSE74-A23445
Articles are hosted by Taylor and Francis Online.
A control-rod optimization problem is formulated for a one-dimensional multiregion reactor; that is, the end-of-life state surfaces are formulated in the N-dimensional bumup space, which is an N-dimensional Euclidean space, with its axis corresponding to the macroscopic fission cross section of each region. Solutions for a three-region reactor model are derived by using the principle of optimality. The investigation of these solutions reveals the existence of unique and nonunique solutions, depending on the relationship of end-of-life state surfaces. The relationship between two kinds of solution is discussed.