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
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
February 2026
Nuclear Technology
January 2026
Fusion Science and Technology
Latest News
DOE, General Matter team up for new fuel mission at Hanford
The Department of Energy's Office of Environmental Management (EM) on Tuesday announced a partnership with California-based nuclear fuel company General Matter for the potential use of the long-idle Fuels and Materials Examination Facility (FMEF) at the Hanford Site in Washington state.
According to the announcement, the DOE and General Matter have signed a lease to explore the FMEF's potential to be used for advanced nuclear fuel cycle technologies and materials, in part to help satisfy the predicted future requirements of artificial intelligence.
Charles W. Townley, James E. Howes, Jr., Gilbert E. Raines, Ward S. Diethorn, Duane N. Sttnderman
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 346-351
doi.org/10.13182/NSE61-A15376
Articles are hosted by Taylor and Francis Online.
A radiochemical technique has been developed for the determination of the release rates of short-lived fission gases from fuel specimens during irradiation. Fission-product gases with half-lives ranging from 1.7 sec to 3.9 min were employed in the development of the procedure. These were krypton-89, xenon-137, xenon-140, and xenon-141. The procedure involves the collection and analysis of the solid daughter products of these gases. The gases are swept through a long tube packed with stainless steel mesh, and the daughter products deposit on the mesh as they are formed. The mesh is analyzed radiochemically for the daughter species, strontium-89, cesium-137, barium-140, and cerium-141. From the results of these analyses, the release rates of the parent fission gases may be calculated with a knowledge of the transit time of the gases through the tran and the transport time from the point of release to the trap entrance.