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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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.
Nobuo Sasamoto, Kiyoshi Takeuchi
Nuclear Science and Engineering | Volume 80 | Number 4 | April 1982 | Pages 554-569
Technical Paper | doi.org/10.13182/NSE82-A18969
Articles are hosted by Taylor and Francis Online.
A numerical method is presented for calculating neutron transport problems in three-dimensional (x,y,z) geometry on the basis of a method of direct integration of the integral transport equation. Several new techniques are introduced to the method to make it well adapted to practical neutron transport calculations in three-dimensional geometry. A technique for evaluating the scattering source based on an estimated spectral shape in each material region allows use of coarse energy mesh intervals without reducing calculational accuracy as compared with the calculation with fine meshes. A quadratic function approximation for the source spatial distribution in each spatial mesh interval is found to improve the mathematical error in direct integration of the source term over the spatial variable as compared with the linear- or exponential-function approximation used in the original method. In addition, Lagrange's interpolation formula is applied instead of the linear interpolation used in the original method for more accurate estimation of both flux and source. Comparisons are made of the calculations with experiments for three neutron transport problems, the pool critical assembly experiment, the Winfrith iron benchmark experiment, and the annular duct neutron streaming experiment, and also with the three-dimensional Sn calculation to verify the validity of the present method for neutron transport calculations in (x,y,z) geometry.
