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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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
Thea Energy releases preconceptual plans for Helios fusion power plant
Fusion technology company Thea Energy announced this week that it has completed the preconceptual design of its fusion power plant, called Helios. According to the company, Helios is “the first stellarator fusion power plant architecture that is realistic to build and operate with hardware that is available today, and that is tolerant to the rigors of manufacturing, construction, long-term operation, and maintenance of a commercial device.”
Gary S. Hoovler, M. Neil Baldwin, Ray L. Eng, Fred G. Welfare
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 217-237
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Fuel | doi.org/10.13182/NT80-A32604
Articles are hosted by Taylor and Francis Online.
Close-packed storage of light water reactor (LWR) fuel assemblies is needed to expand the capacity of existing underwater storage pools. This increased capacity is required to store the large volume of spent fuel that arises from prolonged on-site storage. To provide benchmark criticality data in support of this effort, an experimental program sponsored by the U.S. Department of Energy was undertaken. Low-enriched UO2 fuel pins in a water-moderated lattice were used to construct 20 critical assemblies that simulated a variety of close-packed LWR fuel storage configurations. The critical assemblies consisted of nine LWR-type fuel assemblies (clusters) grouped in a radially reflected 3×3 array. Both the spacing and material between the fuel clusters were varied to provide numerous critical configurations. All pertinent data for each critical assembly are documented in sufficient detail to validate calculational methods according to the American National Standards Institute standard N16.9-1975. Criticality calculations using the Monte Carlo code KENO IV were performed for comparison with the experimental data. The comparison shows that the calculational model underestimates keff when separation between fuel clusters is >1 pin pitch (1.64 cm), and that the degree of underestimation increases as the spacing widens.