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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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.
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.