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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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.
G. Dharmadurai
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 345-349
Technical Paper | doi.org/10.13182/NSE83-A15455
Articles are hosted by Taylor and Francis Online.
A simple acoustic mismatch model can predict heat flow across solid/fluid interfaces at high temperatures in terms of known physical properties of the system. Using this model, the thermal boundary conductances of the various interfaces involved in heat transfer from the fuel pellet to the cladding of fast reactor fuel rods are estimated. The typical values of fuel-cladding gap conductance of helium-bonded fast reactor fuel rods quoted in the literature are in reasonable agreement with estimates obtained from this model. In addition to its striking simplicity, an interesting and novel feature of this fundamental approach is the prediction of a marginally high gap conductance for a helium-bonded oxide fuel rod over its carbide counterpart.