ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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!
Latest Magazine Issues
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
AI at work: Southern Nuclear’s adoption of Copilot agents drives fleet forward
Southern Nuclear is leading the charge in artificial intelligence integration, with employee-developed applications driving efficiencies in maintenance, operations, safety, and performance.
The tools span all roles within the company, with thousands of documented uses throughout the fleet, including improved maintenance efficiency, risk awareness in maintenance activities, and better-informed decision-making. The data-intensive process of preparing for and executing maintenance operations is streamlined by leveraging AI to put the right information at the fingertips for maintenance leaders, planners, schedulers, engineers, and technicians.
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.
