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Conference 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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New coolants, new fuels: A new generation of university reactors
Here’s an easy way to make aging U.S. power reactors look relatively youthful: Compare them (average age: 43) with the nation’s university research reactors. The 25 operating today have been licensed for an average of about 58 years.
E. G. Schlechtendahl
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 99-114
Technical Paper | doi.org/10.13182/NSE70-A20368
Articles are hosted by Taylor and Francis Online.
Sodium boiling situations in a fast-reactor fuel element can be calculated with the BLOW-2 code from their initiation until fuel-pin failure occurs. The model, which is used, is substantiated by means of a theoretical analysis of the cause of the typical piston-type bubble generation, and it is checked against water and sodium tests. Typical examples of sodium boiling incidents are given. The probability of occurrence of severe nuclear excursions generated by sodium boiling is calculated.
