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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2024 ANS Winter Conference and Expo
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Orlando, FL|Renaissance Orlando at SeaWorld
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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.
L. R. Fawcett, Jr.
Nuclear Science and Engineering | Volume 113 | Number 2 | February 1993 | Pages 173-183
Technical Paper | doi.org/10.13182/NSE93-A24006
Articles are hosted by Taylor and Francis Online.
Tritium production in a sphere of 6LiD with an Oralloy core irradiated by a central source of 14-MeV neutrons has been calculated and compared with experimental measurements. The experimental assembly consisted of an Oralloy sphere surrounded by three solid 6LiD concentric shells with ampoules of 6LiH and 7LiH located in several positions throughout the assembly. The Los Alamos Monte Carlo Neutron Photon Transport Code (MCNP) was used to calculate neutron transport throughout the system and tritium production in the ampoules. The MCNP calculations were three-dimensional and employed ENDF/B- V cross sections. The overall experimentally observed-to-calculated ratios of tritium production were 0.996 (±2.5%) in 6LiH ampoules and 0.903 (±5.2%) in 7LiH ampoules. Tritium production in a sphere of 6LiD without an Oralloy core has been reanalyzed using ENDF/B-V cross sections, and the results are reported. The reanalyzed observed-to-calculated values of tritium production were 1.053 (±2.1%) in 6LiH and 0.999 (±2.1%) in 7LiH. The foregoing several uncertainties do not include an estimated <6% systematic error in the observed values.