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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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.
L. A. Semenza, E. E. Lewis, E. C. Rossow
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 302-310
Technical Paper | doi.org/10.13182/NSE72-A22416
Articles are hosted by Taylor and Francis Online.
The finite element method is applied to the multigroup neutron diffusion equations. The one-group inhomogeneous diffusion equation is first discretized using both triangular and rectangular elements. The finite element method is then extended to energy-dependent diffusion by treating the multigroup equations as a series of inhomogeneous one-group equations with sources arising from fission and group-to-group scattering. The resulting formalism is incorporated into a computer code for solving multigroup criticality problems by poweriteration techniques. Numerical results are presented for a two-group water reactor problem. Eigenvalues and flux distributions obtained from two finite element calculations using less than 500 simultaneous equations are in excellent agreement with an accurate PDQ calculation.