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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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.
N. K . Ganguly, F. C. Cobb, A. W. Waltner
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 223-226
Technical Paper | doi.org/10.13182/NSE63-A28883
Articles are hosted by Taylor and Francis Online.
Measurements of the diffusion parameters of heavy water were made using a 1 Mev Van de Graaff accelerator utilizing the Be9(d, n) reaction under pulsed operation. The measurements were made at temperatures of 10°, 20°, 31°, 40°, and 50°C for buckling values ranging from 0.063 cm−2 to 0.100 cm−2. The decay of the neutron density was measured by a BF3 counter, located under the moderator container, in conjunction with a 26-channel time analyzer. The meanlife for each buckling was computed using Peierls' method; and values of the diffusion parameters were computed by the method of least squares. The value of the diffusion constant, (2.00 ± 0.04) × 105 cm2/sec at 10°C, agreed within the limits of experimental error with that found by Raievski and Horowitz, who used the modulated source method. The coefficient of the B4 term, usually referred to as the diffusion cooling coefficient, was found to be (3.72 ± 0.50) × 105 cm4/ sec as compared with (3.5 ± 0.8) × 105 cm4/sec as reported by Sjostrand in 1959.