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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
R. H. Rainey, J. G. Moore
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 367-371
doi.org/10.13182/NSE61-A15380
Articles are hosted by Taylor and Francis Online.
The Acid Thorex process has been developed on a laboratory scale for recovery of uranium and thorium from spent fuel solutions. The thorium and uranium are extracted by tributyl phosphate (TBP) with only the thorium nitrate and nitric acid as “salting agents.” As compared to the present Thorex process in which aluminum nitrate is employed as a salting agent, a considerably greater reduction in aqueous waste volumes is possible. With a synthetic solution of Consolidated Edison Thorium Reactor fuel as feed, uranium and thorium were decontaminated from ruthenium, zirconium-niobium, protactinium, and rare earth elements by factors of 2,000, 30,000, 1,000, and 105, respectively. The concentrated aqueous waste volume was 0.2 liter per kilogram of thorium processed. These values compare favorably with corresponding decontamination factor values for the aluminum-salted Thorex system of 600, 3,000, 3,000, and 2 × 105 and volume of 2 liters per kilogram of thorium processed.