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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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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!
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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.
S. S. Glickstein, P. H. Lehmann, L. L. Wheat, J. D. Korsmeyer, S. Milani, G. G. Smith, S. H. Weiss
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 122-136
Technical Paper | doi.org/10.13182/NSE67-A17249
Articles are hosted by Taylor and Francis Online.
Thermal disadvantage factor measurements in cells of seed-blanket assemblies containing highly enriched 235U and 233U fuel rods as well as in cells containing slightly enriched 233U fuel rods are in agreement within experimental uncertainties with calculations for all but a very tightly packed blanket lattice. The measurements were corrected for flux perturbations in the fuel rod and the moderator channel caused by the detecting foils. MARC calculations using the Radkowsky scattering kernel yield results approximately 8% higher than similar calculations using the Nelkin kernel. While THERMOS calculations for the tightly packed blanket cells appear to be in agreement with measurement (possibly fortuitous), MARC results are significantly above the measured values. The source of the discrepancy is not known at this time. Higher order scattering as well as angular energy effects in the source-to-thermal neutron energy treatment have been investigated using a newly developed full energy range (0 to 10 MeV) Monte Carlo program RECAP-4C.
