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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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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.
D. V. Gopinath, K. Santhanam
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 186-196
Technical Paper | doi.org/10.13182/NSE71-A21266
Articles are hosted by Taylor and Francis Online.
A semi-analytical technique for the solution of neutron and gamma-ray transport in one-dimensional finite systems is developed. The method is applicable to multivelocity, multiregion systems with arbitrary degree of anisotropy. The transport equation is written in the form of coupled integral equations separating the spatial and energy-angular transmissions. Legendre polynomial approximation in the direction cosine, and discrete ordinate representation in energy and spatial domain are used for radiation source and flux. The space and energy-angle transmission kernels are evaluated analytically and the integral equations are then solved by a fast-converging iterative technique. For a plane parallel beam of radiation incident on a slab, the virgin and the first collision flux are not amenable to polynomial expansion due to the singularities. For such a case, up to second collision, source is computed analytically and then recourse is taken to polynomial approximation. The computer code ASFIT written on the basis of the above formulation is briefly described. Convergence studies with the polynomial approximation, energy and spatial mesh width are described.