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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
U. Fischer, E. Wiegner
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2174-2179
Blanket Shield and Neutronic | doi.org/10.13182/FST92-A30042
Articles are hosted by Taylor and Francis Online.
The 14 MeV neutron transport in spherical iron assemblies is analyzed on the basis of different computational procedures and new double-differential 56Fe cross-sections (DDX) from the ENDF/B-VI and EFF-2 data files. Comparisons with existing integral 14 MeV neutron experiments and with calculations using uncorrected energy-angle distributions show significant improvements due to the inclusion of DDX-data in the recent fusion-oriented data files. Further analyses are required as the total neutron leakages measured in the referenced integral experiments still are underestimated.
