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Design and Analysis of the Experimental Gas-Cooled Reactor Fuel Assemblies

G. SAMUELS

Nuclear Science and Engineering / Volume 14 / Number 1 / September 1962 / Pages 37-52

Technical Paper / dx.doi.org/10.13182/NSE62-A26198

The design of the Experimental Gas-Cooled Reactor fuel assemblies is described and a brief outline of the experimental heat transfer and fluid dynamic studies and mechanical testing is presented. Correlations derived from the experimental data are given, and the results of their application to the fuel element analysis are shown. The hot channel factors are described, and the expected fission gas pressure buildup within the elements is discussed.