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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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
NRC grants Clinton and Dresden license renewals
Three commercial power reactors across two Illinois nuclear power plants—Constellation’s Clinton and Dresden—have had their licenses renewed for 20 more years by the Nuclear Regulatory Commission.
Paritosh Chaudhuri, P. Santra, S. K. S. Parashar, D. Chenna Reddy
Fusion Science and Technology | Volume 63 | Number 1 | January 2013 | Pages 59-65
Technical Note | doi.org/10.13182/FST12-489
Articles are hosted by Taylor and Francis Online.
Plasma-facing components (PFCs) are an important part of the Indian Steady State Superconducting Tokamak (SST-1) design. The main consideration in the design of PFCs is steady-state heat removal of up to 1 MW/m2 , which is nearly the limit for incident heat flux of mechanically attached graphite tiles for tokamak PFCs. SST-1 PFCs consist of divertors, passive stabilizers, baffles, and limiters and are designed for long-pulse operation, which requires active cooling of these components. During steady-state operation, the average heat loads on the divertor and passive stabilizers are expected to be 0.6 and 0.25 MW/m2 , respectively. Design considerations include two-dimensional steady-state and transient tile temperature distribution and the resulting thermal loads in PFCs during plasma operation. Thermal analysis is carried out to evaluate the thermomechanical behavior of the SST-1 PFCs. In this technical note, temperature distribution and thermally induced stresses and strains in PFCs are analyzed using a finite element method, and the effect of stress and strain on different materials used in PFCs is discussed.