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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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August 2024
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.
J. F. Carew, A. L. Aronson, D. M. Cokinos, A. Prince, M. Todosow
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 279-285
Technical Paper | doi.org/10.13182/NSE85-A17304
Articles are hosted by Taylor and Francis Online.
A simple and accurate analytic method for calculating pressure vessel neutron damage >1-MeV fluence has been derived. The method employs asymptotic expressions for the one-speed neutron transport Green's function, together with an effective removal cross section, to propagate the neutron source from the core out to the pressure vessel. The spatial integration over the core neutron source is performed using a multipole expansion of the transport Green's function. The analytic method reproduces detailed (DOT) numerical calculations in both (r,ϴ) and (r,z) geometries to within 5%, and similar accuracy is expected in three dimensions.