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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Argonne researching “climate-ready” nuclear plant design
Scientists at Argonne National Laboratory have partnered with Washington state–based Energy Northwest to look at alternative ways to cool nuclear reactors as climate change impacts relied-upon water sources.
B. F. Picologlou, Y. S. Cha, S. Majumdar
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 848-853
Liquid-Metal Blankets and Magnetohydrodynamic Effects | Proceedings of the Seveth Topical Meeting on the Technology of Fusion Energy (Reno, Nevada, June 15–19, 1986) | doi.org/10.13182/FST86-A24843
Articles are hosted by Taylor and Francis Online.
The reactors considered in the Tokamak Power Systems Studies (TPSS), with their reduced toroidal magnetic flux densities, increased aspect ratios, and moderate overall power outputs afford the possibility of significant improvements and simplification in the design of liquid-metal self-cooled blankets. In designing the first wall and blanket structural, thermal, and magnetohydrodynamic constraints must be satisfied simultaneously. A systematic approach to do so efficiently, and resulting design parameters are presented. Designs with separate limiters can achieve a neutron wall loading capability of about 5 MW/m2 with bare structural walls near the first wall and insulated laminated construction in regions of low fluence only. When laminated wall construction is used in the first wall coolant channels, the neutron wall loading capability exceeds 10 MW/m2.