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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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.
Neil Mitchell, Denis Bessette, Hirobumi Fujieda, Yuri Gribov, Cees Jong, Fabrice Simon
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 676-684
ITER | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A8987
Articles are hosted by Taylor and Francis Online.
The ITER magnet system, particularly the Poloidal Field Coils (PFC) and Central Solenoid Coils (CSC), was originally designed to drive, confine and stabilise a set of plasmas about a baseline of a reference 15MA 400s inductive burn, with capability for inductive short burn at currents up to 17MA and 10MA non-inductive plasmas depending on the plasma parameters that can be achieved.Recent assessments of experimental data and improved plasma modelling have identified some constraints in the 2001 design that may limit the range of plasmas that can be generated in ITER. The constraints are a mixture of coil superconducting performance, structural and electrical limits, and concern both the accuracy of the formation of the plasma configuration (including the position of the separatrix lines in the divertor) and the stabilisation of the plasma position.