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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
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.
R. C. Lloyd, S. R. Bierman, E. D. Clayton, B. M. Durst
Nuclear Science and Engineering | Volume 78 | Number 2 | June 1981 | Pages 121-125
Technical Paper | doi.org/10.13182/NSE81-A20098
Articles are hosted by Taylor and Francis Online.
A series of experiments was performed to determine the effect of gadolinium as a soluble neutron absorber on the criticality of fuel rod assemblies in uranyl nitrate solution. The gadolinium in the form of Gd(NO3)s was mixed with uranyl nitrate solution. The lattice assemblies were composed of 4.3 wt% 235U-enriched UO2 pellets contained in stainless steel tubes immersed in the uranyl nitrate solution of the same 235U enrichment. Lattice assemblies with center-to-center fuel rod separations of 22.9, 27.9, and 33.0 mm were utilized in this study. In each case, a preset number of fuel rods was positioned in the assembly vessel and uranyl nitrate subsequently added, with the measurement then being of the depth of solution required for criticality. The uranyl nitrate was limited to the fuel-rod-bearing region of the lattice assemblies that were, in turn, reflected with water. Data on integral critical experiments are provided against which calculational techniques can be checked.