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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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.
Ç. Ertek, A. Yalçin, Y. İnel
Nuclear Science and Engineering | Volume 36 | Number 2 | May 1969 | Pages 209-219
Technical Paper | doi.org/10.13182/NSE69-A19718
Articles are hosted by Taylor and Francis Online.
An experimental method of determining the ratio of the epicadmium 238U neutron-capture rate to the subcadmium 238U capture rate in a fuel rod, (ρ28), is presented. The precision is ∼0.3% on the cadmium ratio. The relative 239Np and fission-product activities induced in a representative cross section of the fuel material (a thin bare foil of natural uranium) are compared with those induced in a cadmium-covered identical foil in a “flux symmetric” position in the rod. The 239Np gamma activity is counted by a coincidence method with and without the application of chemical separation. The results from the coincidence method are compared with two single-channel and one hundred-channel analyzer results obtained by chemical separation.