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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.
Douglas W. Stamps
Nuclear Science and Engineering | Volume 157 | Number 3 | November 2007 | Pages 331-343
Technical Paper | doi.org/10.13182/NSE07-A2731
Articles are hosted by Taylor and Francis Online.
A general analytical model was developed to predict the thermal-hydraulic behavior in box-type catalytic recombiners of different sizes and configurations. The fluid mechanics of the recombiner was modeled as flow through a chimney, which resulted in a modified form of the classic chimney equation to predict the exit gas velocity and flow rate. The thermal behavior of the recombiner was modeled using the transient form of the energy equation for reacting flow. The model was assessed using data from recombiners developed by the NIS Ingenieurgesellschaft Company (NIS), Siemans, and Atomic Energy of Canada Limited. Good agreement was obtained between the model and experimental data for the time-dependent hydrogen concentration in the test facility and the capacity of the recombiner in terms of the hydrogen recombination rate, both key parameters in the analyses of accidents in nuclear power plants. The analytical model could be reduced to the form of an empirical correlation developed for the NIS recombiner under simplifying conditions.