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Division Spotlight
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.
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.
S. Inoue, Y. Taji, Y. Nakahara, T. Suzuki
Nuclear Science and Engineering | Volume 73 | Number 2 | February 1980 | Pages 119-124
Technical Paper | doi.org/10.13182/NSE80-A18692
Articles are hosted by Taylor and Francis Online.
Transport of neutral particles in a toroidal plasma is treated in the same manner as that of neutrons by the Monte Carlo method. A new sampling technique of flight-path length is proposed for the torus geometry. Several routines relating to the toroidal geometry have been developed and incorporated into the neutron and gamma-ray transport Monte Carlo code “MORSE.” Results obtained from sample calculations to check the cylindrical approximation show that hot neutrals escape more easily from the torus than from the cylinder, while cold neutrals are retained better in the cylinder. Furthermore, the spectrum of the leakage neutrals is compared with the neutral and ion spectra inside the torus.