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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.
Sergey I. Belousov, Krassimira D. Ilieva
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 239-244
Technical Paper | doi.org/10.13182/NSE97-A24477
Articles are hosted by Taylor and Francis Online.
A new adjoint synthesis (ASYNT) method is proposed for synthesizing a three-dimensional solution from two- and one-dimensional solutions of the adjoint neutron transport equation. Its correctness and fast run ability are appropriate for evaluating neutron irradiation for the VVER/pressurized water reactor pressure vessel—especially for surveillance sites located out of the reactor core midplane.The solution axial dependence in circular cylindrical geometry is the main approximation used. The ASYNT method could be reduced to the traditional synthesis method by some supplementary approximations. The solution for every type of reactor is obtained by calculating the adjoint neutron transport equation only once for each surveillance site.