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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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Nuclear Science and Engineering
Fusion Science and Technology
New polls show substantial support for nuclear energy
Sixty percent of respondents in a recent national survey favored the use of nuclear energy, with only 25 percent opposing its use. While the latest Bisconti Research poll focuses on nuclear power and electricity generation, its findings on public interest in climate change and using a spectrum of sources to meet energy needs are consistent with a recent Pew Research Center poll on a broad set of energy policy and climate change topics. The approaches the two online surveys took to measuring public opinion on nuclear energy yielded different numbers but found some common ground.
M. Lipa, J. Schlosser, F. Escourbiac
Fusion Science and Technology | Volume 56 | Number 3 | October 2009 | Pages 1124-1149
Technical Papers | Tore Supra Special Issue | dx.doi.org/10.13182/FST09-A9171
Articles are hosted by Taylor and Francis Online.
To fulfill the Tore Supra mission (the realization and study of high-performance long-duration discharges), the development of reliable actively cooled plasma-facing components is mandatory. This was foreseen from the beginning of Tore Supra, and since 1985, the Tore Supra team has been involved in the development and fabrication of actively cooled plasma-facing components. The initial configuration of the machine in 1988 included a 12 m2 inner first wall made of stainless steel tubes armoured with brazed graphite, outer water-cooled stainless steel panels, and modular pump limiters. This configuration, using the inner wall as limiter, allowed 20- to 30-s-duration plasma discharges to be performed. Further progress required the development of a more reliable brazing technique and a limiter support system mechanically independent of the vacuum vessel. A new configuration (Composants Internes et Limiteur project), using a completely new concept of high-heat-flux components (including notably a braze-free bond between carbon-fiber composite tiles and copper heat sink), was therefore launched in 1997. With this new configuration, discharges up to 6 min with 1 GJ of injected and removed power were achieved in 2003.