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Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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The U.S. Million Person Study of Low-Dose-Rate Health Effects
There is a critical knowledge gap regarding the health consequences of exposure to radiation received gradually over time. While there is a plethora of studies on the risks of adverse outcomes from both acute and high-dose exposures, including the landmark study of atomic bomb survivors, these are not characteristic of the chronic exposure to low-dose radiation encountered in occupational and public settings. In addition, smaller cohorts have limited numbers leading to reduced statistical power.
Dawn E. Janney, Steven L. Hayes, Cynthia A. Adkins
Nuclear Technology | Volume 206 | Number 1 | January 2020 | Pages 1-22
Critical Review | doi.org/10.1080/00295450.2019.1623617
Articles are hosted by Taylor and Francis Online.
Although U-Pu-Zr alloys have been investigated for more than 60 years, relatively little experimental information is available, and many of the original values are in government reports that appeared more than 40 years ago. Information about the technologically important alloy U-20Pu-10Zr (weight percent) is even more limited. Since U-Pu-Zr alloys are difficult materials to study experimentally, it is therefore important to understand what results have already been obtained, how reliable they are, and where they were reported.
This critical review provides a summary and critical assessment of the available experimental measurements of thermal and mechanical properties of U-Pu-Zr alloys. Knowledge of these properties is crucial for understanding and modeling fuel constituent redistribution, fuel swelling and creep, fission gas release under normal reactor operations, and melting or formation of liquid phases under reactor transient scenarios.
This critical review builds on a previous review that assessed experimental data about phases and phase diagrams in U-Pu-Zr alloys. Both reviews are intended as resources for fuel designers and modelers and as guides for prioritizing future experimental work.