Mark I containment evaluation short term program. Final report. Addendum 3. Vent header and vent pipe impact loads
Technical Report
·
OSTI ID:7343638
Pool swell and subsequent impact loads are produced as a result of the purging of the air in the drywell into the torus during a postulated loss-of-coolant accident (LOCA). Included in this Addendum are the magnitude, duration and time of the initiation of the impact loads on the vent system. Information is presented on a plant unique basis so that the utilities may combine the impact loads with the hydrodynamic pressure loads applicable to the specific plant (Reference 4) in the performance of an evaluation of the torus support system structural capability under the combined loads. This report concludes the documentation of the loads to be used in the Mark I Short Term Program.
- Research Organization:
- General Electric Co., San Jose, Calif. (USA). Boiling Water Reactor Systems Dept.
- OSTI ID:
- 7343638
- Report Number(s):
- NEDC-20989(Add.3)
- Country of Publication:
- United States
- Language:
- English
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210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
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CONTAINMENT SYSTEMS
DYNAMIC LOADS
ENGINEERED SAFETY SYSTEMS
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LOSS OF COOLANT
MECHANICAL STRUCTURES
PRESSURE GRADIENTS
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WATER MODERATED REACTORS