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.
Floro Miraldi, Melville Clark, Jr.
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 246-255
Technical Paper | doi.org/10.13182/NSE61-A25999
Articles are hosted by Taylor and Francis Online.
The critical parameters of coupled, fissionable assemblies in close proximity to one another are studied by differential equations for the conservation of neutrons. The coupling between the assemblies is taken into account by the use of approximate boundary conditions derived from expressions for the average neutron flow between the assemblies. Critical equations are found from the one and two group diffusion theories and from the P3 approximation/The results are compared with existing experimental data. The present methods are especially suited to the study of arrays of prisms.
