ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
DOE-EM finishes cleanup of legacy Oak Ridge reactor lab site
The Department of Energy’s Office of Environmental Management announced that the 30-foot-long, 37,600-pound reactor vessel from Oak Ridge National Laboratory’s Low Intensity Test Reactor was shipped to EnergySolutions’ low-level radioactive waste facility in Clive, Utah, in late April.
Yasuhide Senda, Seiji Shiroya, Masatoshi Hayashi, Keiji Kanda
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 318-334
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A15959
Articles are hosted by Taylor and Francis Online.
The results of analyses on the void reactivity measurements performed in the Kyoto University Critical Assembly using medium-enriched uranium fuel as well as highly enriched uranium fuel are provided. In consideration of the heterogeneity of a complex core, four-group constants were generated by SRAC, a standard thermal reactor code system for reactor design and analysis at the Japan Atomic Energy Research Institute. The eigenvalue and perturbation calculations were subsequently performed by the 2D-FEM-KUR code, which is a two-dimensional diffusion code based on the finite element method. The calculated eigenvalue keff agreed with the measured value to within 0.5% in the calculated-to-experiment ratio. The void reactivity calculated by perturbation theory approximately reproduced the experimental data including the spatial dependence. The discrepancy between the calculated and measured void reactivity was <0.05 × 10−3 Δ k / k per voided flow channel.