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
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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
W. D. Burch, E. D. Arnold, A. Chetham-Strode
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 438-442
Technical Paper | doi.org/10.13182/NSE63-A17395
Articles are hosted by Taylor and Francis Online.
Gram quantities of many of the transuranium elements through californium-252 will be produced for research purposes in a production program centered at Oak Ridge National Laboratory. Plutonium-242 produced in the Savannah River production reactors will be transmuted to various higher actinide isotopes in the High Flux Isotope Reactor (thermal flux—3 × 1015 neutrons/ cm2-sec) and recovered in the adjoining Transuranium Processing Plant. Calculations which optimized the production scheme are presented. The intermediate goal of the program, production of one gram of Cf252, should be accomplished by 1968.