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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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Latest News
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
H. Takenaga, H. Kubo, Y. Kamada, Y. Miura, Y. Kishimoto, T. Ozeki
Fusion Science and Technology | Volume 50 | Number 4 | November 2006 | Pages 503-507
Technical Paper | doi.org/10.13182/FST06-A1273
Articles are hosted by Taylor and Francis Online.
Accumulation of impurity injected for reduction of heat load to the divertor plates was of great concern with a peaked density profile. Applicability of impurity injection to a burning plasma with a peaked density profile was investigated for various impurity accumulation levels using the A-SSTR2 design parameters. Impurity transport analysis indicated that the argon density profile twice as peaked as the electron density profile can yield acceptable radiation profile even with a peaked density profile. The required confinement improvement factor over the IPB98(y,2) scaling slightly increased from 1.4 with the flat density profile to 1.5 with the peaked electron density profile at ne(r/a = 0)/ne(r/a = 0.7) ~ 3. When the argon density profile was determined by neoclassical transport, the radiation loss in the core plasma intensively increased with the peaked density profile, which requires higher confinement enhancement factor of 1.9 at ne(r/a = 0)/ne(r/a = 0.7) ~ 3.