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Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
Comanche Peak adds years to operating licenses
The Nuclear Regulatory Commission has renewed the operating licenses of Comanche Peak Units 1 and 2 for an additional 20 years.
Unit 1’s operating license now expires on February 8, 2050, and Unit 2’s on February 2, 2053.
O. Gastaldi, P. Aizes, F. Gabriel, J. F. Salavy, L. Giancarli
Fusion Science and Technology | Volume 54 | Number 1 | July 2008 | Pages 101-106
Technical Paper | Blanket Design | doi.org/10.13182/FST08-A1774
Articles are hosted by Taylor and Francis Online.
Within the framework of the development of technology for a fusion reactor, the need of tritium breeding in order to reach fuel self-sufficiency is a major issue.The systems allowing this tritium production (breeding blanket) have to deal with a main difficulty that comes from the tendency for tritium to diffuse through hot metallic walls. Because of the double function of the blanket: i) breeding the necessary Tritium and ii) efficiently extracting the deposited heat, the coolantcontaining metallic surfaces used to promote the heat transfer lead also to a non negligible mass transfer of tritium from the breeder material towards the coolant.In order to improve the management of tritium, different studies have been launched in this field with applications to DEMO breeding blankets and to the corresponding Test Blanket Module (TBM) to be tested in ITER. The present paper is focused on the case of the helium cooled lithium lead (HCLL) blanket which is one of the two TBMs proposed by EU for testing in ITER.The study determines, for different scenarios of ITER operation (short pulse, long pulse and trains of back-to-back pulses), the flux of tritium between each circuit (mainly PbLi breeder and He coolant), and the inventories of tritium in each circuit. The establishment of mass balance equations for tritium in each circuit leads to a set of non linear differential equations solved in transient conditions since ITER pulses are too short to reach steady state. These equations rely mainly on Fick's law with a link to the tritium Sievert's constant in each metal.