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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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
First GAIN vouchers of 2025 go to Curio, Deep Fission, Kairos, and NuCube Energy
The Department of Energy’s Gateway for Accelerated Innovation in Nuclear (GAIN) has awarded four fiscal year 2025 vouchers to support the development of advanced nuclear technologies. Each company will get access to specific capabilities and expertise in the DOE’s national laboratory complex—in this round of awards both Idaho National Laboratory and Pacific Northwest National Laboratory are named—and will be responsible for a minimum 20 percent cost share, which can be an in-kind contribution.
Shekhar Kumar, Sudhir Babu Koganti
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 279-283
Technical Note | Reprocessing | doi.org/10.13182/NT00-A3062
Articles are hosted by Taylor and Francis Online.
The solubilities of nonelectrolytes in aqueous electrolyte solutions have traditionally been modeled by using the Setschenow equation for salt effect. The aqueous solubility of tri-n-butyl phosphate (TBP) during operating conditions of the Purex process is an important parameter for safety considerations. Use of the Setschenow equation for aqueous solubility of TBP under limited conditions has been reported in the literature. However, there is no general model available to account for the presence of the diluent and for the case of multicomponent electrolyte solutions in which only some electrolytes are solvated and extracted by TBP. An extended salt effect model is proposed for predicting the aqueous solubility of TBP in a 5 to 100% TBP/n-dodecane-nitric acid-water biphasic system at 298.2 K. The literature data on TBP solubility were correlated to aqueous acid concentration, diluent concentration in the solvents, and an interaction parameter for electrolytic solutes (extracted or not extracted by TBP).