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The tests conducted on the 1/5-scale BWR Mark I pressure suppression test facility simulate the three-dimensional transient conditions that are encountered in a wetwell pressure suppression system during a hypothetical loss-of-coolant accident (LOCA). Specifically, the nitrogen (N2)-driven air clearing phase tests discussed were performed to obtain the air/water-induced dynamic vertical load function and to determine the response of a 90° sector of a 360° torus structure.
Language: en
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Pages:
The tests conducted on the 1/5-scale BWR Mark I pressure suppression test facility simulate the three-dimensional transient conditions that are encountered in a wetwell pressure suppression system during a hypothetical loss-of-coolant accident (LOCA). Specifically, the nitrogen (N2)-driven air clearing phase tests discussed were performed to obtain the air/water-induced dynamic vertical
Language: en
Pages: 35
Pages: 35
Books about Proposed Sale of La Crosse Boiling Water Reactor to Dairyland Power Cooperative
Language: en
Pages: 30
Pages: 30
Language: en
Pages:
Pages:
Books about Burnout Limit Curves for Boiling Water Reactors
Language: en
Pages: 48
Pages: 48
Language: en
Pages:
Pages:
Books about LA CROSSE BOILING-WATER REACTOR-SAFEGUARDS REPORT FOR OPERATING AUTHORIZATION.
Language: en
Pages: 78
Pages: 78
A methodology has been developed to extract generic risk-based information from probabilistic risk assessments (PRAs) of General Electric boiling water rectors and applying the insights gained to plants that have not been subjected to a PRA. The available risk assessments (six plants) were examined to identify the most probable, i.e.,
Language: en
Pages: 29
Pages: 29
Books about Dynamic analysis of natural circulation boiling water power reactors
Language: en
Pages: 471
Pages: 471
Linear and Non-Linear Stability Analysis in Boiling Water Reactors: The Design of Real-Time Stability Monitors presents a thorough analysis of the most innovative BWR reactors and stability phenomena in one accessible resource. The book presents a summary of existing literature on BWRs to give early career engineers and researchers a
Language: en
Pages: 141
Pages: 141
"In the design of novel nuclear reactors active systems are replaced by passive ones in order to reduce the risk of failure. For that reason natural circulation is being considered as the primary cooling mechanism in next generation nuclear reactor designs such as the natural circulation boiling water reactor (BWR).