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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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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. Kelley, B. L. Twitty
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 374-377
Technical Paper | doi.org/10.13182/NSE62-A26179
Articles are hosted by Taylor and Francis Online.
An improved neutron activation procedure for determining the U235 content in impure uranium samples is presented. With 95% confidence, a relative precision of ±1% is obtained at the level of 0.7 wt % U235. An ethyl acetate extraction is used to purify the uranium chemically. Most of the uranium decay products are removed by extraction with 2-thenoyltrifluoroacetone (TTA) in xylene. The purified uranium, which is subsequently activated as U3O8, has a consistent gamma background level. Utilization of a i.d. well scintillation crystal has permitted the use of large diameter aluminum planchettes holding 2 gm aliquots of U3O8. This system has minimized the problem of varying irradiation geometries caused by differences in U3O8 bulk density. Data from a sample recycle program are presented to illustrate the relative precision of ±1%. Comparisons between neutron activation and mass spectrometric results agree within ±1%.