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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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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.
Charles E. Cartmill
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 422-427
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32348
Articles are hosted by Taylor and Francis Online.
A Semiscale Mod-1 blowdown heat transfer test was conducted to supply thermal-hydraulic data concerning the fluid phenomena that occur during a small break loss-of-coolant accident. While it is easily recognized that a large break suddenly releases a great volume of coolant with rapidly falling levels and pressures, emergency core injection will also occur very early, compared to a small break. There has been concern that the longer times involved in small breaks (much longer subcooled flow periods) could lead to effects worse than for large breaks. Within the scope of the testing conducted, the small break has proven to be of lower consequences than the large break.