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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.
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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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Fusion Science and Technology
Latest News
Argonne to investigate Pu chemistry to aid Hanford cleanup
Researchers at the Department of Energy’s Argonne National Laboratory are investigating the details of plutonium chemistry with the goal of aiding the cleanup of the Hanford Site in Washington state. For more than 40 years, reactors located at Hanford produced plutonium for America’s defense program, resulting in millions of gallons of liquid radioactive and chemical waste.
M. E. Fenstermacher, R. S. Devoto, R. H. Bulmer, J. D. Lee, J. R. Miller, J. H. Schultz
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 740-745
Plasma Heating and Current Drive-I | doi.org/10.13182/FST89-A39784
Articles are hosted by Taylor and Francis Online.
The physics and engineering guidelines for the ITER device are shown to lead to viable physics operating points for a steady state tokamak power reactor. Non-inductive current drive is provided in steady state by high energy neutral beam injection in the plasma core, lower hybrid slow waves in the outer regions of the plasma and bootstrap current. Plasma gain Q (≡ fusion power/input power) in excess of 20 and average neutron wall loading, <Γ> ≈2.0 MW/m2 are predicted in a device with major radius, R0 = 7.5 m and minor radius, a = 2.8 m.