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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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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
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.
Masaki Taniguchi, Kazuyuki Nakamura, Kazuyoshi Sato, Koichiro Ezato, Kenji Yokoyama, Masato Akiba
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 890-893
Divertor and Plasma-Facing Components | doi.org/10.13182/FST01-A11963352
Articles are hosted by Taylor and Francis Online.
Disruption erosion tests on La2O3 containing and pure tungsten materials were performed by the electron beam irradiation facility. As a result, it was found that the disruption erosion of La2O3 – W evaluated from the weight loss was three times larger than that of pure – W. The surface observations suggest that the splashing of the melted layer during the electron beam irradiation occurs only for the La2O3 – W, which results in the larger weight loss in disruption erosion. This is considered to be due to the lower melting point of the added La2O3.
