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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Nuclear News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
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.