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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.
Richard B. Jones, Morton Tavel
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 90-92
Technical Note | doi.org/10.13182/NSE75-A40349
Articles are hosted by Taylor and Francis Online.
The accuracy of the phase space time evolution method applied to neutron transport is contrasted with a one-dimensional discrete ordinates code with anisotropic scattering, ANISN, a time-dependent explicit discrete ordinates code, TIMEX, and theoretical benchmark values for critical bare slabs. The comparison is performed by calculating the critical value of v (the number of neutrons released per fission) for slabs of various halfwidths. Furthermore, pointwise flux differences are displayed for one particular slab thickness. Finally, a nonlinear time-dependent problem previously solved only in diffusion theory is considered.