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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
R.D. Watson, F.M. Hosking, M.F. Smith, C.D. Croessmann
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1794-1798
Impurity Control and Plasma-Facing Component | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29603
Articles are hosted by Taylor and Francis Online.
The monoblock geometry is proposed for the ITER Physics Phase divertor for brazing of carbon armor tiles to copper or molybdenum cooling tubes. Elastic/plastic finite element analyses predicted high residual stresses except with OFHC copper. Samples of pyrolytic graphite tiles brazed to OFHC copper, Glidcop™ Al-15 copper alloy, and molybdenum tubing show cracking in all of the samples, except with the OFHC copper. A 3-tile divertor target consisting of 12 mm thick pyrolytic graphite brazed with a copper-silver alloy to a 12 mm diameter OFHC copper tubing was tested at 15 MW/m2 with a rastered 30 keV electron beam for 1000 thermal cycles. A gradual rise in surface temperature from 1000 C to 1200 C over the 1000 cycles was observed, along with hot stripes (1500 C) at the tile edges. However, no delamination cracks could be detected.
