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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Hiromichi Fumoto, Erich Zimmer, Ryohei Kiyose, Erich R. Merz
Nuclear Technology | Volume 58 | Number 3 | September 1982 | Pages 447-464
Technical Paper | Chemical Processing | doi.org/10.13182/NT82-A32980
Articles are hosted by Taylor and Francis Online.
Received December 28, 1981 Accepted for Publication March 22, 1982 Two 5-m pulse columns with the same cartridge geometries have been installed for Thorex process studies. First, the differences of the aqueous and the organic continuous modes of operation have been investigated. Flow characteristics and extraction efficiencies of acetic acid and thorium nitrate have been obtained. Then, the uranium and thorium coextraction and partitioning have been carried out. The concentration profiles of thorium, uranium, and nitric acid along columns have been determined for the coextraction and the partitioning process and the Height Equivalent Theoretical Stage values have been calculated from these data.