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.
Douglas W. Akers, Richard K. McCardell
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 264-272
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27653
Articles are hosted by Taylor and Francis Online.
The partitioning and release of fission products from fuel materials in the Three Mile Island Unit 2 (TMI-2) reactor pressure vessel (RPV) are summarized, and the chemistry that resulted in the observed behavior is discussed. As part of the TMI-2 core examination program, samples were examined from all regions within the RPV, from leadscrews in the upper plenum to previously molten material from the lower plenum of the RPV. The results of these examinations indicate significant variations in fission product behavior that were generally consistent with the volatility and chemical behavior of the expected fission product species. Low-volatility species (e.g., 144Ce) were retained almost entirely in the fuel material matrix, whereas unoxidized species such as 125Sb were found with the metallic structural materials. Most of the high-volatility species (137Cs and 129I) were released from the previously molten fuel; however, the releases were less than expected. These fission products were retained in previously molten fuel that contained concentrations of structural materials at the grain boundaries.