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
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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Nuclear Science and Engineering
October 2024
Nuclear Technology
Fusion Science and Technology
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.
Shunsuke Uchida, Masao Kitamura, Shunichi Miyasaka
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 155-159
Technical Note | doi.org/10.13182/NSE78-A27134
Articles are hosted by Taylor and Francis Online.
Experiments were undertaken to determine the distribution of neutron flux on the core support grid plate of liquid-metal fast breeder reactors by using a semimockup of the grid-plate shield consisting of carbon-steel and aluminum slabs. The experiments were calculated with a conventional calculational procedure containing the TRD-3 two-dimensional removal diffusion code. It was demonstrated that the calculated radial distribution of the fast neutron reaction rates of 115In(n,n′)115mIn agreed with the measured values within a factor of 2.
