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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
WHAM: Realta gets first plasma with 17 Tesla magnets in mirror fusion test
The magnetic mirror fusion concept dates to the early 1950s, but decades ago it was sidelined by technical difficulties and researchers turned to tokamak fusion in their quest for confinement. Now it’s getting another look—with significantly more powerful technology—through WHAM, the Wisconsin HTS Axisymmetric Mirror, an experiment in partnership between startup Realta Fusion and the University of Wisconsin–Madison.
Masahiro Ueta, Masakazu Ichimiya, Hiroshi Hirayama, Masayuki Asano, Hisaaki Ikeuchi, Katsuhisa Sekine, Tetsuhiko Kodama, Kenichiro Sato
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 1-12
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34749
Articles are hosted by Taylor and Francis Online.
The core support structure of a fast breeder reactor supports the fuel assemblies, supplies sodium coolant to the fuel assemblies, and maintains the insertability of control rods even during an earthquake. The core support structure is designed as a box fabricated of welded plates, ribs, and cylinders that distribute the load in a diverse manner, in order to reduce the weight and to fulfill safety-related functions. This box structure was not adopted in the Monju prototype reactor; thus, a method to evaluate the structural integrity of this structure must be developed. To prepare design guidelines, structural integrity was studied in accordance with the requirements and features of the box structure. This study consisted of the evaluation of crack propagation under loadings on cracks with hypothetical dimensions as well as an ordinary structural design method. To clarify the crack propagation behavior, partial-scale model tests were conducted that simulated typical core support structure parts. From the results of these experiments, the crack growth rate was evaluated and incorporated into the structural integrity evaluation method. Finally, the structural integrity of the core support structure of the Japanese demonstration reactor is evaluated by this method.