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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Moltex demonstrates its WATSS fuel recycling process
Advanced reactor company Moltex Energy Canada said it has successfully validated its waste to stable salt (WATSS) process on used nuclear fuel bundles from an unnamed Canadian commercial reactor through hot cell experiments conducted by Canadian Nuclear Laboratories.
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%.
