ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
Latest Magazine Issues
Mar 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
Richard M. Bidwell
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 426-434
Technical Paper | doi.org/10.13182/NSE64-A18760
Articles are hosted by Taylor and Francis Online.
Chemical behavior of fission products is predicted for a “dynamic core” fast reactor, where the fuel is pumped through an outside loop by the coolant. For a 7.5 at % Pu/25 at % Co/67.5 at % Ce alloy, the various fission products are classified as sodium-extractable, fuel-soluble, precipitating, and rare gases. Evidence predicting the behavior of each class is presented. The rates of extraction of removable fission products are estimated for different modes of operation. Extractable fission product atoms are expected to remain in the fuel phase for only a few seconds. Sixty percent of all of the fission product atoms formed remain in solution in the fuel phase, and occupy a volume (∼35% of that of all fission products) roughly equal to that of the Pu consumed. The consumption of the initial inventory of Pu would require the gradual addition of 110% of the original amount of Pu, of which 3% is required to compensate for poisoning. The effective chemical composition of the fuel would be little changed during “100% burn-up.” A dynamic-core fast reactor can be operated for several years as a continuous chemical system at an economic burn-up rate.