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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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Nuclear Science and Engineering
August 2024
Nuclear Technology
July 2024
Fusion Science and Technology
Latest News
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Michiko Ahn Furudate, Seungyon Cho
Fusion Science and Technology | Volume 71 | Number 4 | May 2017 | Pages 514-519
Technical Paper | doi.org/10.1080/15361055.2017.1293417
Articles are hosted by Taylor and Francis Online.
The equilibrium chemical compositions of purge gas at the outlet of the Test Blanket Module in Helium Cooled Ceramic Reflector (HCCR) Test Blanket System are studied. Mole fractions of H, T, O, H2, HT, T2, H2O, HTO, and T2O in the equilibrium state are calculated by a Gibbs free energy minimization method starting from the initial state of H2/HTO mixture. The standard Gibbs free energy for tritium species obtained by the density functional theory is used in the calculations. The tritium recovery rates in the form of HT, T2, HTO and T2O are estimated from the equilibrium chemical compositions obtained in the calculations. The effects of H2 concentration in the purge gas on the tritium recovery process are also investigated by parametric study with variations of purge gas flow rate and volume ratio of hydrogen to helium in the purge gas.