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.
Chia-Jung Hsu
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 380-388
Technical Note | doi.org/10.13182/NSE72-A22426
Articles are hosted by Taylor and Francis Online.
The heat transfer characteristics of a rod which is dislocated from its symmetrical position are studied analytically for slug flow through tightly packed rod bundles (P/D ratio down to ≈1.00). Explicit equations describing the temperature fields in the fuel core, the cladding, and the elemental coolant flow area are obtained by assuming uniform fuel power density. Variation of the rod-average Nusselt number, as well as the heat flux distribution at the outer wall of the cladding, is examined for selected values of σ, the P/D ratio, the cladding thickness parameter, λ(=r1/r2) and the thermal conductivity ratios, κ and κw. The present solutions, when specialized to the case of σ = 0.0 (i.e., no rod displacement) show excellent agreement with the results reported by Axford and by Dwyer and Berry who studied the corresponding three-region and two-region problems, respectively, for symmetrical rod bundles with no rod displacement.