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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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Fusion Science and Technology
Latest News
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Stanley M. Kaye, Masayuki Ono, Yueng-Kay Martin Peng, Donald B. Batchelor, Mark D. Carter, Wonho Choe, Robert Goldston, Yong-Seok Hwang, E. Fred Jaeger, Thomas R. Jarboe, Stephen Jardin, David Johnson, Robert Kaita, Charles Kessel, Henry Kugel, Rajesh Maingi, Richard Majeski, Janhardan Manickam, Jonathan Menard, David R. Mikkelsen, David J. Orvis, Brian A. Nelson, Franco Paoletti, Neil Pomphrey, Gregory Rewoldt, Steven Sabbagh, Dennis J. Strickler, Edmund Synakowski, James R. Wilson
Fusion Science and Technology | Volume 36 | Number 1 | July 1999 | Pages 16-37
Technical Paper | doi.org/10.13182/FST99-A88
Articles are hosted by Taylor and Francis Online.
The mission of the National Spherical Torus Experiment (NSTX) is to prove the principles of spherical torus physics by producing high-t plasmas that are noninductively sustained and whose current profiles are in steady state. The NSTX will be one of the first ultralow-aspect-ratio tori (R/a 1.3) to operate at high power (Pinput up to 11 MW) to produce high-t (25 to 40%), low-collisionality, high-bootstrap-fraction (70%) discharges. Both radio-frequency and neutral beam heating and current drive will be employed. Built into the NSTX is sufficient configurational flexibility to study a range of operating space and the resulting dependences of the confinement, micro- and magnetohydrodynamic stability, and particle- and power-handling properties. NSTX research will be carried out by a nationally based science team.