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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
2020 ANS Virtual Winter Meeting
November 16–19, 2020
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U.S. reactor technologies to be featured at IAEA conference
A virtual side event at the 64th General Conference of the International Atomic Energy Agency will spotlight U.S. reactor technologies. The free event, US Reactor Technologies: Flexible Energy Security for Real-World Challenges, will be held this Thursday, September 24, from 9:00 a.m. to 10:30 a.m. (EDT).
The event will highlight the capabilities of small modular reactors and other innovative reactors for addressing countries’ current needs. It will also examine anticipated challenges in the future, as well as underscore the need to act now.
The event is sponsored by the U.S. Department of Energy’s Office of Nuclear Energy. Advanced registration is required.
Dawn E. Janney, Steven L. Hayes, Cynthia A. Adkins
Nuclear Technology | Volume 206 | Number 1 | January 2020 | Pages 1-22
Critical Review | dx.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.