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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.
Richard W. Benjamin, John A. Harvey, Nathaniel W. Hill, Madhu S. Pandey, Robert F. Carlton
Nuclear Science and Engineering | Volume 85 | Number 3 | November 1983 | Pages 261-270
Technical Paper | doi.org/10.13182/NSE83-A17318
Articles are hosted by Taylor and Francis Online.
The neutron total cross sections of 249Bk and 249Cf have been measured from 0.03 to 100 eV using the Oak Ridge Electron Linear Accelerator as a source of pulsed neutrons. The 1.6-mm-diam cylindrical transmission samples initially contained up to 5.3 mg of 98% 249Bk and 2% 249Cf; 4.5 yr later, when the final measurements were made, the composition of the samples had become 2.5% 249Bk, 96.9% 249Cf and 0.6% 245Cm. Samples were cooled with liquid nitrogen to reduce Doppler broadening. Thirty-nine resonances were identified in 249Bk and analyzed using a single-level Breit-Wigner formalism. Fifty-five resonances were identified in 249Cf and analyzed using an R-matrix multilevel formalism. The resonance parameters obtained have been used to determine the average level spacings and the s-wave neutron and fission strength functions. Where possible, bound-level parameters were derived to fit the thermal neutron total cross-section data.