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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
A. E. Hechanova, M. S. Kazimi
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1880-1886
Plasma-Facing Component | doi.org/10.13182/FST92-A29993
Articles are hosted by Taylor and Francis Online.
A divertor composed of beryllium-coated copper tubes was analyzed for lifetime performance for near-term tokamaks. The thermal hydraulic analysis revealed the need for enhancing coolant heat transfer in order to avoid boiling in the water-cooled tube. The insertion of twisted tapes at the strike points was found to increase the heat transfer coefficient by more than 90 percent (from 59 to 113 kW/m2-K) and allow a 3 mm thick beryllium armor to remain below the desirable safety limit of 1073 K. Under normal operation, sputtering was estimated to result in an erosion rate of 0.0027 mm per 200-s pulse. Hard thermal quenches (plasma disruptions) were found to be the critical life-limiting divertor issue since up to 0.3 mm of beryllium could be vaporized per disruption event. This would require armor regeneration after 10 such disruptions. An analysis of the copper tube stresses suggests that primary and secondary stresses remain below their allowable limits under normal operations provided the ends of the plate are not restrained and allow for expansion.