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2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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Christmas Light
’Twas the night before Christmas when all through the house
No electrons were flowing through even my mouse.
All devices were plugged by the chimney with care
With the hope that St. Nikola Tesla would share.
R. Nijsing, W. Eifler
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 289-299
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32329
Articles are hosted by Taylor and Francis Online.
The present version, THARC-S, of the transient thermohydraulic subassembly code, THARC, under development at the Joint Research Centre at Ispra, has been applied to predict the transient thermohydraulic behavior of liquid-metal fast breeder reactor subassemblies subjected to loss-of-flow conditions. Information is given on the present status of development of THARC. Computational results are presented for 217-rod subassemblies, both for grid and wire spacers. It is shown that radial power gradients and overcooling in the region adjacent to the wrapper wall cause boiling inception in the subassembly to be incoherent with, as a consequence, a more gradual boiling and voiding process than expected on the basis of a one-dimensional approach. It is demonstrated that heat capacity effects associated with the fuel rods and the wrapper wall are of considerable importance. Aspects associated with code validation in out-of-pile bundle experiments are also briefly discussed.