
doi: 10.2172/4749308
An investigation was conducted to determine the effects of He leakage through EGCR moderator columns and fuel element sleeves on the core coolant flow distribution reported in study II-179-1. Results of the investigation are discussed and recommendations for design changes so that the total coolant bypass will remain the same as previously reported are made. (J.R.D.)
Reactor Technology, Planning, Losses, Graphite Moderator, Egcr, Gas Coolant, Distribution, Gas Flow, Reactors, Porosity, Helium, Power Plants, 620
Reactor Technology, Planning, Losses, Graphite Moderator, Egcr, Gas Coolant, Distribution, Gas Flow, Reactors, Porosity, Helium, Power Plants, 620
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