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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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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.
K. Serdula, J. Young
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 40-50
Technical Paper | doi.org/10.13182/NSE65-A19761
Articles are hosted by Taylor and Francis Online.
The neutron diffusion and integral scattering properties of graphite have been measured by the pulsed-neutron-source technique. Measurements were performed on assemblies with geometric bucklings from 0.0036 to 0.0151 cm−2. The time of attainment of asymptotic neutron-energy spectra was determined from transmission measurements. Results from these latter measurements indicated that the minimum thermalization time, for the assemblies investigated, was ≈ 2 msec. Asymptotic ‘average’ neutron velocities, measured both internally and externally, were obtained as a function of assembly size. Results indicated that an asymptotic neutron spectrum did not exist for assemblies with B2 ≈ 0.015 cm−2 at a time 2 msec after the neutron pulse. A value of the diffusion cooling coefficient, C = 45.6 ± 4.7 × 105 cm4/sec was derived from the measured ‘thermal’ neutron decay constants.