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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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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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.
M. C. Chuang, M. D. Carelli, C. W. Bach, J. S. Killimayer
Nuclear Science and Engineering | Volume 64 | Number 1 | September 1977 | Pages 244-257
Technical Paper | doi.org/10.13182/NSE77-A27095
Articles are hosted by Taylor and Francis Online.
A study is presented to determine the detailed coolant velocity and temperature profile around the entire rod circumference in liquid-metal fast breeder reactor (LMFBR) core assemblies as well as the detailed radial and circumferential temperature profile in the rod. The digital computer code FATHM-360 developed to perform the above calculations is described. Fuel, radial blanket, and control assembly rods (both wire-wrapped and bare) can be analyzed. Coolant, cladding, and fuel (or absorber) temperature profiles are calculated for uniform and nonuniform heat generation (i.e., accounting for power skew across the pellet) in the rod. Temperature distributions can be calculated for both concentric and eccentric positions of the pellet with respect to the fuel rod cladding. Typical examples of the calculational capabilities of the code are presented. Such capabilities are needed for a reliable design of LMFBR core assemblies and rods to provide detailed cladding temperature profiles and accurately calculate the cladding strain on which the fuel rod lifetime and allowable burnup depend. Overall, a more realistic core thermofluids design is possible by implementing the study presented here.