ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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Latest News
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.
G. Bitelli, M. Salvatores
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 309-314
Technical Paper | doi.org/10.13182/NSE69-A18729
Articles are hosted by Taylor and Francis Online.
In this paper a multigroup method in finite monodimensional geometry is presented for neutron distribution calculation from a given source distribution. This method is extended to neutron importance function calculation for a given detector distribution. Furthermore, it is shown how truncating the calculation at whatever collision, it is possible to evaluate the “residual” neutron distribution by means of usual methods in diffusion or transport theory. An application is presented related to the generalized perturbation methods and the numerical solution of problems of general interest.
