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
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Japan gets new U for enrichment as global power and fuel plans grow
President Trump is in Japan today, with a visit with new Prime Minister Sanae Takaichi on the agenda. Takaichi, who took office just last week as Japan’s first female prime minister, has already spoken in favor of nuclear energy and of accelerating the restart of Japan’s long-shuttered power reactors, as Reuters and others have reported. Much of the uranium to power those reactors will be enriched at Japan’s lone enrichment facility—part of Japan Nuclear Fuel Ltd.’s Rokkasho fuel complex—which accepted its first delivery of fresh uranium hexafluoride (UF₆) in 11 years earlier this month.
Kazuhiko Akamine, K. J. Hofstetter, V. F. Baston
Nuclear Technology | Volume 84 | Number 2 | February 1989 | Pages 152-168
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34184
Articles are hosted by Taylor and Francis Online.
On commencing defueling operations in the Three Mile Island Unit 2 (TMI-2) reactor vessel damaged core region, the defueling water cleanup system (DWCS) encountered rapid plugging of its filter media. Characterization of the suspended material was an important task in resolving DWCS filtration difficulties. The characterization of the suspended material involved laboratory analyses of reactor vessel coolant samples collected from May through November 1986. The results of these characterizations indicated that the major elements present in the suspended particles were silver, aluminum, cadmium, iron, indium, silicon, uranium, and zirconium, all of which correspond to the five known source terms in the TMI-2 reactor vessel (control rod alloy, zeolite, diatomaceous earth, steel, fuel, and Zircaloy cladding). The particle analysis data indicate that the majority of particles were <5 µm and many of these suspended particles existed as colloidal particles; hence, these particulates are believed to have been the principal basis for filter plugging. In addition, based on these characterization data and data from previous analyses of reactor components, it was postulated that some mass fraction of the liquefied control rod alloy formed aerosols from mechanical formation due to high-velocity gas interaction with the moving liquid alloy.