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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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
December 2023
Nuclear Technology
Fusion Science and Technology
November 2023
Latest News
Argonne assists advanced reactor development with award-winning safety software
The development of modern nuclear reactor technologies relies heavily on complex software codes and computer simulations to support the design, construction, and testing of physical hardware systems. These tools allow for rigorous testing of theory and thorough verification of design under various use or transient power scenarios.
Yuri Igitkhanov, Boris Bazylev, Lorenzo Boccaccini
Fusion Science and Technology | Volume 75 | Number 7 | October 2019 | Pages 642-646
Technical Paper | doi.org/10.1080/15361055.2019.1610291
Articles are hosted by Taylor and Francis Online.
The impact of the edge-localized modes (ELMs) on the tungsten divertor erosion by taking into account the screening effect of vapor shielding is analyzed for DEMO steady-state operation condition. The evaluation of tungsten ablation, energy radiation, and absorption by divertor plate due to a single ELM impact is calculated by using a model of vapor shielding inserted in the MEMOS code. The effect of repetitive ELM impact and the tungsten melt layer formation is described by using the model of W monoblock with a compliance layer of Cu alloy between the W and EUROFER water cooling tube.
It is shown that the vapor plasma shielding results in saturation of the single ELM energy accumulated by the divertor plate and that the saturation level depends on the ELM duration. The ablation thickness can reach about 0.01 µm. The total number of ablated particles is rather critical for the shielding formation, and the lifetime of the divertor plate depends strongly on this effect.