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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Cheol Ho Pyeon, Kota Morioka
Nuclear Science and Engineering | Volume 196 | Number 10 | October 2022 | Pages 1147-1160
Technical Paper | doi.org/10.1080/00295639.2022.2070385
Articles are hosted by Taylor and Francis Online.
Nuclear data–induced uncertainty of criticality is successfully analyzed by combining the eigenvalue calculations, the uncertainty, and the reduction of uncertainty with the use of the KENO-VI code, the TSUNAMI-3D and the TSURFER modules of the SCAL6.2.4 code system, respectively. The comparative study of conventional and revised S(α, β) applications is also conducted by KENO-VI. Notably, the KENO-VI analyses reveal the difference between the experimental and numerical results of criticality and the neutron spectrum dependence of criticality on the H/U ratio in the solid-moderated and solid-reflected cores at the Kyoto University Critical Assembly (KUCA). The difference is identified as the leading cause of uncertainty in the 235U fission spectrum (χ value) through the combined use of the uncertainty and the cross-section adjustment by TSUNAMI-3D and TSURFER, respectively, especially that the highly enriched uranium (HEU) fuel is loaded into the KUCA cores. Also, the neutron spectrum dependence of criticality is attributable to the uncertainty induced by the cross-section data of 235U capture, 27Al elastic scattering, and inelastic scattering reactions in the HEU fuel plate and to the 1H capture reactions in the polyethylene moderator through the TSUNAMI-3D analyses.