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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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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.
Walter Meyer, J. W. Leighty, J. W. Thiesing, D. H. Timmons
Nuclear Science and Engineering | Volume 60 | Number 4 | August 1976 | Pages 405-420
Technical Paper | doi.org/10.13182/NSE76-A26902
Articles are hosted by Taylor and Francis Online.
Albedos were experimentally determined for a spectrum of fast fission neutrons incident on a 24- × 24- × 9-in. concrete slab and a 24- × 24- × 6-in. cold-rolled steel slab. The experimental dose albedos were compared with those from Oak Ridge National Laboratory (ORNL) 05R Monte Carlo calculations and with orders-of-scattering calculations performed using readily available multigroup cross sections. The source of fast neutrons for the experimental studies was the Kansas State University Triga Mark II reactor; the direct and reflected neutron spectra were detected using a 2- × 2-in. liquid-scintillation spectrometer system. A computer code has been developed to normalize the experimental reflected spectra to a reference direct neutron beam measurement, to calculate the experimental dose albedos, and to evaluate the Monte Carlo dose albedos in terms of the experimental conditions. A comparison of the Monte Carlo and experimental results showed similar trends and structure, but the experimental dose albedos were smaller than the calculated ones by an average of 70 to 80%. The large energy bin widths and inaccuracies in the cross sections (errors up to 65%) used in the Monte Carlo calculations have contributed to the differences between the calculated and experimental results. Orders-of-scattering calculations for steel were performed using the ORNL DLC-2B 99-group cross-section set and similar calculations were performed for concrete using the DLC-9/FARS group cross-section set. In general, the orders-of-scattering calculated reflected spectra compare well with the experimental fast-neutron reflection spectra. Discrepancies arise in the orders-of-scattering calculated results at particular energies and scattering angles due to deficiencies identified in the multigroup compilations.