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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.
Shanqi Chen, Daochuan Ge, Zhen Wang, Jiangtao Jia, Zhibin Chen, Liqin Hu
Fusion Science and Technology | Volume 74 | Number 3 | October 2018 | Pages 238-245
Technical Note | doi.org/10.1080/15361055.2018.1461966
Articles are hosted by Taylor and Francis Online.
No-public evacuation is an expectation for fusion power plants (FPPs) from the public and governments. In this technical note, a preliminary consequence assessment of an ITER wet bypass–like accident (the accident with the most severe consequence in ITER) of a helium-cooled deuterium-tritium tokamak FPP is performed and compared with that of ITER. Ideal gas–based methodology is proposed to evaluate the released materials in accidents, which is verified by typical accident cases in FPPs. The verification indicates that, compared with the best estimated codes, the proposed method is much simpler and easier with effectiveness. The accident assessment shows that this helium-cooled FPP design may still need public evacuation if the accident happens, which demonstrates the requirement of further investigations for FPP accidents. Some suggestions are proposed to improve the safety of FPPs based on the assessment.