ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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August 2024
Latest News
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. Forman, F. A. White
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 139-143
Technical Paper | doi.org/10.13182/NSE67-A18677
Articles are hosted by Taylor and Francis Online.
The thermal-neutron capture cross section of 147Sm has been measured by the mass spectrometric determination of the number of 148Sm atoms formed by neutron capture. Samples of high isotopic purity were irradiated in a well-thermalized neutron spectrum for which the time-integrated neutron flux and effective neutron temperature were monitored by the burnup in 149Sm and 157Gd. A thermal-neutron capture cross section value of 75 ± 11 b was obtained from a post-irradiation 148Sm/ 147Sm ratio of 0.00025 ± 8%, at an effective neutron temperature of 127 ± 13°C.
