ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
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.
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.
H. D. Brown
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 687-693
Technical Paper | doi.org/10.13182/NSE57-A25436
Articles are hosted by Taylor and Francis Online.
The solution of the equations describing the reactor state is obtained by numerical integration of the differential equations on an IBM-650. The general description includes the dependence of lattice constants and absorption cross sections upon the temperatures of various components and accommodates the effects of manipulations of the geometric buckling and of the total absorption cross section. The reactor kinetic equations are put into difference form suitable for numerical solution. Measures are described for eliminating divergences introduced by the numerical treatment of the coupling among temperature coefficients, delayed neutrons, and flux.