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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
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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Jeffrey King guides new nuclear program at Tennessee Tech
Jeffrey King
In August, the College of Engineering at Tennessee Technological University welcomed ANS member Jeffrey C. King as the founding director of its new nuclear engineering program. King, a leading force within the American Nuclear Society and a space enthusiast, is tasked with developing a new Department of Nuclear Engineering at Tennessee Tech after a more than 20-year absence of such a program at the university.
King comes to Tennessee Tech from the Colorado School of Mines, where he had been a professor of metallurgical and materials engineering for 15 years, leading the development of the nuclear science and engineering program and serving as director of the Nuclear Science and Engineering Research Center.
Caishan Jiao, Hao Wang, Yaorui Li, Meng Zhang, Yang Gao, Mingjian He
Nuclear Technology | Volume 208 | Number 12 | December 2022 | Pages 1858-1866
Technical Paper | doi.org/10.1080/00295450.2022.2081483
Articles are hosted by Taylor and Francis Online.
With the rapid development of nuclear power, increasing attention has been paid to the treatment of low-level radioactive wastewater (LLRW). In this study, reverse osmosis (RO) and membrane distillation (MD) are used to treat LLRW containing Ce(III), U(VI), and Co(II). RO was used for the purification of LLRW. MD was used for further concentration of RO concentrate. The effect of the operating parameters, including operating pressure (0.6 to 1.4 MPa), feed pH (7 to 9), feed concentration (2 to 10 mg/L), feed temperature (50°C to 90°C), and feed flow rate (80 to 160 L/h) on the permeate flux and the rejection rate of the RO process and MD process was studied. The results demonstrate that it is very effective to use the RO process to treat LLRW containing Ce(III), U(VI), and Co(II), with the rejection rates of Ce(III), U(VI), and Co(II) higher than 99.97%, 99.98%, and 99.35%, respectively. The operating pressure has a significant effect on the permeate flux in the RO process. The permeate flux increases from 9.84 to 23.03 L/m2·h when the operating pressure increases from 0.6 to 1.4 MPa. The feed pH has an apparent influence on nuclide rejection. At the feed pH = 9, the rejection rates of Ce(III), U(VI), and Co(II) by the RO process can reach 99.99%, 99.99%, and 99.79%, respectively. MD can reject almost all the nuclides in the RO concentrate, with rejection rates consistently higher than 99.98%. Increasing the feed temperature and feed flow rate can result in a significant increase in the permeate flux, but has almost no effect on nuclide rejection in the MD process.