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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Fusion Science and Technology
Latest News
Zaporizhzhia ‘extremely fragile’ relying on single off-site power line, IAEA warns
Europe’s largest nuclear power plant has just one remaining power line for essential nuclear safety and security functions, compared with its original 10 functional lines before the military conflict with Russia, warned Rafael Mariano Grossi, director general of the International Atomic Energy Agency.
C.P.C. Wong, L. Barlcon, M. Corradini, P. Fogarty, N. Ghoniem, S. Majumdar, S. Malang, R. Mattas, K. McCarthy, B. Merrill, J. Murphy, B. Nelson, R. Nygren, M. Sawan, S. Sharafat, I. Sviatoslavsky, S. Zinkle
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 815-822
Chamber Technology | doi.org/10.13182/FST01-A11963340
Articles are hosted by Taylor and Francis Online.
This paper reports the results of the second phase evaluation of the EVOLVE W-alloy first wall and blanket design cooled by vaporizing lithium. For the transpiration-cooled first wall and blanket concept, we identify the need to further quantify the data of lithium superheat from W-alloy heated surface and bulk lithium slabs. For the boiling lithium blanket, we identify the need to elucidate the impacts of magnetic field on various stable-boiling regimes. We also find that this FW/blanket concept should have no problem in achieving adequate nuclear performance. With the addition of passive cooling loops, the concept has a strong possibility of achieving the safety requirement of not needing a public evacuation plan under the loss of power accident conditions. Even though the irradiated W-alloy may be subject to embrittlement, due to the relatively low system pressure of the design, it is shown to be able to withstand a large number of cracks. The fundamental issues of W-alloy properties under high neutron fluence irradiation and the components fabrication technique remain. Preliminary investigations of W-alloy fabrication and heat flux removal through SBIR programs have begun and the initial results arc encouraging. We recommend that the investigation of critical issues of the EVOLVE concept continue since this innovative design has a good possibility of showing a way to achieve high performance and passively safe designs that are necessary for the utilization of fusion power.