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
Mar 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
April 2026
Latest News
NRC approves TerraPower construction permit
Today, the Nuclear Regulatory Commission announced that it has approved TerraPower’s construction permit application for Kemmerer Unit 1, the company’s first deployment of Natrium, its flagship sodium fast reactor.
This approval is a significant milestone on three fronts. For TerraPower, it represents another step forward in demonstrating its technology. For the Department of Energy, it reflects progress (despite delays) for the Advanced Reactor Demonstration Program (ARDP). For the NRC, it is the first approval granted to a commercial reactor in nearly a decade—and the first approval of a commercial non–light water reactor in more than 40 years.
Jack D. Law, R. Scott Herbst, Dean R. Peterman, Rich D. Tillotson, Terry A. Todd
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 284-290
Technical Paper | Reprocessing | doi.org/10.13182/NT04-A3532
Articles are hosted by Taylor and Francis Online.
A chlorinated cobalt dicarbollide(CCD)/polyethylene glycol (PEG) based solvent extraction process is being developed for the separation of Cs and Sr from leached spent light water reactor (LWR) fuel as part of the Advanced Fuel Cycle Initiative (AFCI). The separation of Cs and Sr would significantly reduce the heat generation of spent nuclear fuel requiring geologic disposal. A solvent composition for this process has been verified, and the distribution coefficient acid dependency for Cs, Sr, Am, and Eu have been measured for the CCD/PEG solvent. Leached spent fuel simulant, traced with 137Cs, 85Sr, 241Am, and 154Eu, was used to perform batch contact flowsheet experiments for the extraction, scrub, and strip sections of the CCD/PEG process. Additionally, the effects of acetohydroxamic acid and its decomposition products, as well as the effects of the uranium extraction (UREX) process solvent, on the extraction of Cs and Sr with the CCD/PEG process were evaluated.