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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Latest News
IAEA again raises global nuclear power projections
Noting recent momentum behind nuclear power, the International Atomic Energy Agency has revised up its projections for the expansion of nuclear power, estimating that global nuclear operational capacity will more than double by 2050—reaching 2.6 times the 2024 level—with small modular reactors expected to play a pivotal role in this high-case scenario.
IAEA director general Rafael Mariano Grossi announced the new projections, contained in the annual report Energy, Electricity, and Nuclear Power Estimates for the Period up to 2050 at the 69th IAEA General Conference in Vienna.
In the report’s high-case scenario, nuclear electrical generating capacity is projected to increase to from 377 GW at the end of 2024 to 992 GW by 2050. In a low-case scenario, capacity rises 50 percent, compared with 2024, to 561 GW. SMRs are projected to account for 24 percent of the new capacity added in the high case and for 5 percent in the low case.
J. Helholtz, W. Rothenstein
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 349-355
Technical Paper | doi.org/10.13182/NSE66-A16404
Articles are hosted by Taylor and Francis Online.
A multigroup procedure for the calculation of the fast fission phenomena in thermal uranium-water reactors has been developed. The method essentially consists of applying the single-flight collision concept in a manner analogous to the calculation of resonance capture in thermal reactor lattices. The collision and escape probabilities are calculated by numerical integration over the actual neutron paths encountered in a reactor lattice. The multigroup equations are solved by an iterative procedure which converges rapidly. The fast neutron spectrum, &dgr;28 and &hexadecimal; can be obtained. Results of calculations are presented in which the value of &dgr;28 homogeneous uranium-water mixtures and for slightly-enriched uranium-water lattices are compared with Monte Carlo calculations and experiment. Very satisfactory agreement has been obtained. Fast neutron spectra in the core of a pool type reactor and in the fuel and moderator regions of a uranium-water lattice, calculated by the present method, are also shown.
