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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Benjamin M. Chase, Anthony W. LaPorta, James R. Parry
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1312-1324
Technical Paper | doi.org/10.1080/00295450.2019.1585162
Articles are hosted by Taylor and Francis Online.
A core characterization process was completed as part of the Transient Reactor Test Facility (TREAT) restart project. The core characterization process is normally performed following a reconfiguration of the TREAT core. This characterization process includes performance of three temperature-limited transients. Prior to performing the transients, analysis is performed using KENO-VI to determine the high-temperature locations and the initiating reactivities for each transient. The point-kinetics code Simulating TREAT Reactor Kinetics (STREK) is used to estimate the peak power, peak temperature, and total energy deposition in the core. STREK also provides plots of pertinent parameters as functions of time to observe time-dependent behavior of the transient. After the transients are complete, the resulting data from these transients are used to develop operating limits for continued operation with the core configuration being characterized. The three transients for the characterization are performed in a progression of increasing initiating reactivity. The first transient has an initiating reactivity of 1.8%Δk/k. The second transient has an initiating reactivity of 3.0%Δk/k. The third transient has an initiating reactivity of 3.85%Δk/k. After the first two transients are performed, a two-point extrapolation of the data is used to determine a temporary estimate of the core operating limits. Once the third transient is complete, the resulting data are fit to an equation, and a three-point extrapolation of the operating limits for the core configuration is generated. This completes the characterization process and provides conservative limits for transient operation of TREAT.