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| Definition Of: | ||
Drywell
The containment structure enclosing a boiling water reactor vessel and its recirculation system. The drywell provides both a pressure suppression system and a fission product barrier under accident conditions.
A service to the public by The U.S. Nuclear Regulatory Commission (NRC).
See also: Anticipated transient without scram , Turbine generator , Fuel temperature coefficient of reactivity , Nucleus , Megacurie |
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International Codes INDEX:List of Terms: Terms beginning with "A", Page 1 |
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Page Number:
1 A: Page 1 of 1. |
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