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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!
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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.
D. B. TRAUGER
Nuclear Science and Engineering | Volume 14 | Number 1 | September 1962 | Pages 69-82
Technical Paper | doi.org/10.13182/NSE62-A26200
Articles are hosted by Taylor and Francis Online.
Irradiation tests have been conducted in the ORR, ETR, and LITR for evaluating fuel materials for the EGCR. Time limitations imposed by the reactor construction schedule restricted material choices and test conditions to those immediately appropriate for the EGCR and necessitated some replication. Fifty-nine assemblies were irradiated at stainless steel cladding surface temperatures of 1300 to 1600°F and power densities both above and below 30,000 Btu/hr per foot of UO2 fuel length. NaK-filled containers were employed to test prototype-size fuel capsules, and air-cooled capsules of reduced size were used for fission-gas-release studies. External pressurization of 315 psia was applied to fuel assemblies of prototype size. Preliminary results appear to affirm the adequacy of the fuel element design.
