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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Y. Maeda, Y. Edao, S. Yamaguchi, S. Fukada
Fusion Science and Technology | Volume 54 | Number 1 | July 2008 | Pages 131-134
Technical Paper | Blanket Design | doi.org/10.13182/FST54-131
Articles are hosted by Taylor and Francis Online.
The diffusion, solution and permeation coefficients of hydrogen isotopes in liquid Li-Pb which is a candidate liquid blanket material for fusion reactors were determined in the temperature range 573-973K using an unsteady permeation method. Each coefficiens was correlated to temperature as follows:DLi-Pb = 1.8 × 10-8 exp(-11590/RT) [m2/s] (1)KLi-Pb = 2.1 × 10-6 exp(-18700/RT) [1/Pa0.5] (2)PLi-Pb = 1.8 × 10-9 exp(-30290/RT) [mol/msPa0.5] (3)The hydrogen permeation flux depends on the square root of pressure at 773-973K. Although the power of pressure declined below 0.4 when temperature was below 673K, the effects of surface resistance were neglected above 673K.The hydrogen solubility in liquid Li-Pbwas found to correlate with a Sievert's constant.We calculated a height-equivalent to theoretical-plate of a gas-liquid countercurrent extraction tower for tritium recovery rates in liquid Li-Pb to beHL = 7.0 × 10-2 [m] (4)
