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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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.
Hans K. Fauske
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 10-17
Technical Paper | doi.org/10.13182/NSE74-A23388
Articles are hosted by Taylor and Francis Online.
This paper discusses some aspects of pin-to-pin failure propagation in a sodium-cooled fast-reactor subassembly resulting from (a) fission-gas release, (b) a local blockage, and (c) release of small amounts of molten fuel. The consequence of a severe flow dilution due to fission-gas release from a highly burned-up fuel pin is shown to give rise to only minor overheating because of the strong effects of fuel heat capacity, radial heat conduction, and mixing. Analysis has also shown that the occurrence of local boiling due to local blockage of detectable size appears unlikely to lead to dryout and flow instability because of the large subcooling effect in the wake downstream of the blockage. Moreover, even if a pin in a fuel assembly is assumed to fail and release small amounts of molten fuel, calculations indicate that heat losses and condensation will prevent any significant pressure generation and void propagation and therefore reduce the likelihood of rapid failure propagation.