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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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
Idaho’s IWTU surpasses tank waste treatment goal
As of last week, crews with Department of Energy cleanup contractor Idaho Environmental Coalition (IEC) processed more than 142,000 gallons of radioactive sodium-bearing tank waste at Idaho’s Integrated Waste Treatment Unit (IWTU) this year.
D. Mandal, D. Sathiyamoorthy, M. Vinjamur
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 150-156
Blanket Materials Technology | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14128
Articles are hosted by Taylor and Francis Online.
Lithium titanate (Li2TiO3) is a potential ceramic material for generation of tritium, which is exploited as a fuel in fusion reactor. However, Li2TiO3 has poor thermal conductivity, due to which thermal management of this material during nuclear reaction is a bottleneck. If this material is used in the form of pebble packed in a column or vessel, namely Test Blanket Module (TBM), the effective thermal conductivity is further brought down due to interstitial voids in the packed bed and also due to point to point contact between spherical pebbles. It is therefore essential to develop a suitable technique to enhance heat transfer properties of a packed pebble bed of Li2TiO3. In the present studies, an attempt has been made to develop a packed fluidized bed wherein particulate Li2TiO3 will be allowed to fluidize in the interstitial void of large stationary pebbles, called packing. Experiments have been carried out on heat transfer from wall to bed in a 162.74-mm-diameter column. Stationary pebbles of Li2TiO3 of size 1 mm to 10 mm and fluidized Li2TiO3 particulate solids of size 231 m to 780 m in the interstitial voids were used. Bed wall temperature in the range of 200°C to 600°C and operating fluidizing gas velocity corresponding to 1-4 times minimum fluidization velocity of fluidized particulate solids in the voids, were used for 20 to 60 volume percent of fluidized particulate solid of Li2TiO3. It has been found that the effective thermal conductivity of packed fluidized bed increased close to the value of thermal conductivity of pure Li2TiO3 at an optimum fluidization velocity corresponding to 2-3 times minimum fluidization velocity depending on fluidized particle, size, its volume fraction and wall temperature.
