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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Latest News
Neely Nuclear Research Center named a nuclear historic landmark
The American Nuclear Society recently announced the designation of three new nuclear historic landmarks: the Hot Fuel Examination Facility, the Neely Nuclear Research Center, and the Oak Ridge Gaseous Diffusion Plant. Today’s article, the second in a three-part series, will focus on the historical significance of the Neely Nuclear Research Center.
David A. Greene
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 218-231
Technical Paper | Reactor | doi.org/10.13182/NT72-A31111
Articles are hosted by Taylor and Francis Online.
A computer code has been written to predict pressure on the shell side of a steam generator during a large scale sodium-water reaction. A typical pressure transient has two main features. An initial pressure spike is followed by a secondary pressure pulse whose amplitude is a function of the inertia forces governing the growth of the hydrogen bubble. Unlike the primary pressure spike which lasts a very short time, the secondary pulse can last for a long time and must be considered a steady-state pressure acting on the shell. Rupture disks under sodium may not provide an effective means of relieving the secondary pressure pulse unless the sodium-water reaction occurs close enough to the disk to cause its rapid failure. It is concluded that both superheater and evaporator units of a reference steam generator design can withstand the pressure transient associated with the sodium-water reaction resulting from a guillotine failure of a single heat transfer tube.