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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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February 2024
Latest News
Kentucky legislature sends nuclear bills to governor
Kentucky’s Republican-majority legislature passed a bill this past week that could bring nuclear energy to the “coal-is-king” state as lawmakers broadly seek solutions to reduce carbon emissions. The bill went to Democratic Gov. Andrew Beshear on Monday for final approval.
M. Zucchetti, L. Candido, Z. Hartwig, R. Po’, S. Segantin, R. Testoni, D. Whyte
Fusion Science and Technology | Volume 75 | Number 6 | August 2019 | Pages 423-428
Technical Paper | doi.org/10.1080/15361055.2019.1613141
Articles are hosted by Taylor and Francis Online.
The new Affordable Robust Compact (ARC) fusion reactor, which, compared to larger machines like ITER, aims to achieve its goal of fusion energy in a less expensive and smaller but even more powerful and faster way with new high-field, high-temperature superconducting magnets, has been designed in the United States. The research tokamak aimed at the development of many ARC technologies is called SPARC. Ignitor is the proposed compact high-field tokamak that shares some design concepts with SPARC and ARC and shows the convenience of this tokamak design development line. Neutronics and radiation damage scoping studies have been carried out for both designs. A general-purpose macroscopic model set up by some of the authors in previous studies has been used to estimate the radiation damage on selected machine components for the two cases. Solutions to solve the problem of radiation damage of the toroidal field coil and poloidal field coil materials have been explored.