Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method

Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method

The nuclear industry has long relied upon bounding parametric analyses in predicting the safety margins of reactor designs undergoing design-basis accidents. These methods have been known to return highly-conservative results, limiting the operating conditions of the reactor. The Best-Estimate Plus...

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Bibliographic Details
Main Author: Hallee, Brian Todd
Other Authors: Wu, Qiao
Language:en_US
Published: 2013
Subjects:
APEX
BEPU
CSAU
DAKOTA
EMDAP
feed and bleed
LOCA
integral test facility
integral effects test
light water reactor
pressurized water reactor
PCT peak cladding temperature
RELAP
response surface
bayesian statistics
wilks method formula
NRC
uncertainty quantification
sensitivity analysis
thermal hydraulic safety analysis
Light water reactors > Safety measures > Mathematical models
Water cooled reactors > Loss of coolant > Mathematical models
Light water reactors > Risk assessment
Nuclear power plants > Thermodynamics > Mathematical models
Online Access:http://hdl.handle.net/1957/37872

Internet

http://hdl.handle.net/1957/37872

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