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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
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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Latest News
Judge temporarily blocks DOE’s move to slash university research funding
A group of universities led by the American Association of Universities (AAU) acted swiftly to oppose a policy action by the Department of Energy that would cut the funds it pays to universities for the indirect costs of research under DOE grants. The group filed suit Monday, April 14, challenging a what it termed a “flagrantly unlawful action” that could “devastate scientific research at America’s universities.”
By Wednesday, the U.S. District Court judge hearing the case issued a temporary restraining order effective nationwide, preventing the DOE from implementing the policy or terminating any existing grants.
Kazuyuki Takase
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 1043-1049
Safety and Environment | doi.org/10.13182/FST01-A11963381
Articles are hosted by Taylor and Francis Online.
Dust-air two-phase flow characteristics in a fusion experimental reactor during a loss-of-vacuum-accident (LOVA) event were analyzed numerically by three dimensional simulations using a newly developed thermal-hydraulic analysis code. Physical models on the motion of dust were considered to resolve the dust mobilization conveying by the fluid. Air ingress behavior through a breach at the LOVA event was calculated by using compressible Navier-Stokes equations. It was predicted quantitatively from the results of the present numerical study that the dust mobilization receives strongly the effect of the breach size and the fraction of the mobilized dust is determined by a circulating flow and buoyancy-driven exchange flow which are generated in a vacuum vessel of the fusion experimental reactor after the LOVA event.