Interim Reliability Evaluation Program Procedures Guide PDF Download
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Author: David D. Carlson
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 153
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Author: David D. Carlson
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 153
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Author: Arthur C. Payne
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages :
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Author:
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ISBN:
Category : Nuclear reactors
Languages : en
Pages :
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Author:
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Category :
Languages : en
Pages :
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Author:
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Category :
Languages : en
Pages :
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Appendices are presented concerning isolation condenser makeup; vapor suppression system; station air system; reactor building closed cooling water system; turbine building secondary closed water system; service water system; emergency service water system; fire protection system; emergency ac power; dc power system; event probability estimation; methodology of accident sequence quantification; and assignment of dominant sequences to release categories.
Author: Arthur C. Payne
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages :
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Category :
Languages : en
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Category : Light water reactors
Languages : en
Pages : 95
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Category :
Languages : en
Pages :
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Probabilistic risk analysis techniques, i.e., event tree and fault tree analysis, were utilized to provide a risk assessment of the Browns Ferry Nuclear Plant Unit 1. Browns Ferry 1 is a General Electric boiling water reactor of the BWR 4 product line with a Mark 1 (drywell and torus) containment. Within the guidelines of the IREP Procedure and Schedule Guide, dominant accident sequences that contribute to public health and safety risks were identified and grouped according to release categories.
Author:
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Category : Nuclear facilities
Languages : en
Pages :
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