ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
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.
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
Robert P. Schuman
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 223-232
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32485
Articles are hosted by Taylor and Francis Online.
There has been considerable controversy concerning the alpha waste and the proliferation hazards of breeder reactors and chemical reprocessing. In order to compare the hazards of different fuel cycles, calculations of alpha waste production and fuel composition have been made for 235U-burning light water reactors (LWRs) and Canadian Deuterium Uranium (CANDU) natural uranium, heavy water reactors using the throw-away fuel cycle, for LWRs with plutonium and uranium recycle, for liquid-metal fast breeder reactors (LMFBRs) using the 238U-239Pu and the 232Th-233U fuel cycles, for LMFBR converters with the 232Th-239Pu fuel cycle, for thermal CANDU breeders and light water breeder reactors using the 232Th-233U fuel cycle, including a 20% denatured CANDU breeder, and for a one-cycle thermal 232Th-239Pu converter. The LWR or CANDU using the throw-away fuel cycle produces the most alpha waste, but the alpha waste, which is due mainly to plutonium, can be greatly reduced by recycling plutonium and uranium. The LMFBR produces still less alpha waste, and, in conjunction with LWRs or CANDUs, minimizes the total inventory of plutonium. Especially if a proliferation-resistant reprocessing scheme is used, the mixed LMFBR/LWR or CANDU economy will greatly reduce the proliferation hazard relative to the throwaway fuel cycle. Recycle of actinide waste in LMFBRs will nearly eliminate the alpha activity of the waste, but will complicate fuel fabrication.