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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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Nuclear Technology
Fusion Science and Technology
February 2024
Latest News
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Yu. Igitkhanov, R. Fetzer, B. Bazylev, L. Boccaccini
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 100-105
Technical Paper | doi.org/10.13182/FST13-732
Articles are hosted by Taylor and Francis Online.
The thermal performance of different modules of plasma-facing components (PFCs) is analyzed for the DEMO reactor conditions in steady-state operation with the inclusion of the transient edge-localized modes (ELMs) for mitigated and unmitigated cases. As an example, the effect of these loads is considered for the tungsten (W) alloy mono-block design with a Cu OFHC/EUROFER water coolant tube first proposed in the framework of the Power Plant Physics and Technology (PPP&T) divertor study. A variant of this design with a EUROFER tube connected to the W block with a diamond/copper composite (DCC) used in the diagnostic windows is also analyzed. A design goal is to find the optimal thicknesses of material layers that allow one to keep the maximum temperatures within the allowable design limits under ITER water cooling conditions. Heat transfer and armor erosion due to the plasma impact has been modeled by using the MEMOS code.