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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Norbert G. Hoogen, Erich R. Merz
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 380-387
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Chemical Processing | doi.org/10.13182/NT83-A33160
Articles are hosted by Taylor and Francis Online.
During the last 20 yr, several potential physical and chemical head-end procedures for graphite-containing high-temperature gas-cooled reactor (HTGR) fuel elements were investigated. In contrast to the principle that the introduction of moderator material into reprocessing should be avoided by all means, with HTGR fuel elements, which consist of ∼95 wt% graphite (moderator material), the primary objective is to remove the bulk of graphite from heavy metals and the fission products. For this purpose, the feasibility of the fluidized bed burning of crushed graphite material has been demonstrated and developed to an advanced stage. If 14C retention is necessary, the CO2 of the burner off-gas can be converted to a solid physical state by fixation of CO2 as CaCO3. Because of the high carbon inventory of the ocean associated with operative dilution effects, controlled dumping of CaCO3 on the deep sea ocean floor could represent safe ultimate disposal