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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
NRC wants input on Hermes 2 test reactor construction permit
The Nuclear Regulatory Commission is seeking input on its draft environmental assessment and draft finding of no significant impact for Kairos Power’s application to build the Hermes 2 test reactor facility in Oak Ridge, Tenn.
B.B. Glasgow, W.G. Wolfer
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 596-601
Blanket and First-Wall Engineering | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40104
Articles are hosted by Taylor and Francis Online.
High heat flux components in fusion reactors will experience inelastic strains resulting from swelling, creep, and thermal expansion. Additionally, because of thermal and irradiation creep, the stresses will redistribute during the lifetime of the component. Current proposals for fusion first walls and divertors include structures fabricated by bonding two different metals together. The plasma side material is chosen to minimize sputtering; the coolant side material is chosen to maximize heat transfer. The structural response of such a design is not well known. Accordingly, a one dimensional inelastic stress analysis of a thin walled shell element has been performed. The stress analysis can include temperature dependent material properties, radiation induced swelling, thermal and irradiation creep, and thermal expansion. Furthermore, a simple equation has been derived for the case of a duplex plate constrained from bending. The stress distribution through the plate is followed with time. It is shown that the initial stress distribution evolves with time until some near steady state distribution is approached. The evolution is dependent on swelling and particularly on creep.