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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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.
E. Goldberg, L. F. Hansen, T. T. Komoto, B. A. Pohl, R. J. Howerton, R. E. Dye, E. F. Plechaty, W. E. Warren
Nuclear Science and Engineering | Volume 105 | Number 4 | August 1990 | Pages 319-340
Technical Paper | doi.org/10.13182/NSE90-A21468
Articles are hosted by Taylor and Francis Online.
Measurements of the neutron and gamma-ray leakage spectra from 15 spherical target assemblies (carbon, nitrogen, H2O, C2F4, aluminum, silicon, titanium, iron, copper, tantalum, tungsten, gold, lead, 232Th, and 238U) pulsed with 14-MeV neutrons were made using time-of-flight techniques. The spheres were ∼30 g/cm2 thick to maximize the gamma-ray leakage per central source neutron. Among all the materials studied, silicon shows the highest conversion factor (∼2 γMeV/n), and lead the lowest (0.31 γMeV/n). Monte Carlo neutron-photon transport calculations were done using the TART and SANDYL codes, with the ENDL and ENDF/B-V libraries. Comparisons with the neutron measurements confirm earlier results, where both libraries reproduced the leakage spectra for most of these materials reasonably well. The gamma spectra calculated with ENDL give a fair representation of the measurements, with the exception of the initial calculations for 16O(H2O) and 19F(C2F4), where serious discrepancies are found. Improvements were obtained for 16O after a re-evaluation of the neutron-induced cross sections based on more recent microscopic experimental data. This was also the case for 19F, where the calculations now overestimate the measurements by 30%. Calculations with the ENDF/B-V are lower than the experimental measurements for most of the materials.