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NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
S. Suzuki, M. Akiba, M. Araki, K. Yokoyama
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1858-1862
Plasma-Facing Component | doi.org/10.13182/FST92-A29989
Articles are hosted by Taylor and Francis Online.
JAERI has been intensively developing plasma facing components for next step large fusion machines, such as ITER (International Thermonuclear Experimental Reactor). It is one of the most important issues to develop divertor plates in the engineering design activity of ITER. The divertor plates are exposed severe heat loads and particle fluxes from fusion plasma. In the operation condition of ITER, the divertor plates are required to withstand a peak heat flux of 15∼30 MW/m2. In the present study, monoblock divertor modules have been manufactured and tested in an electron beam test facility in JAERI, which consist of carbon reinforced carbon composite (CFC) materials brazed on an OFHC copper tube directly. Thermal cycling experiments have been carried out with a peak heat flux of 15 MW/m2. It has successfully been demonstrated that the present design of the ITER divertor plate can endure a stationary heat load of 15 MW/m2 for more than 1000 cycles.
