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

id	ndltd-ORGSU-oai-ir.library.oregonstate.edu-1957-37872
record_format	oai_dc
spelling	ndltd-ORGSU-oai-ir.library.oregonstate.edu-1957-378722013-03-26T03:48:52ZFeed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty methodHallee, Brian ToddAPEXBEPUCSAUDAKOTAEMDAPfeed and bleedLOCAintegral test facilityintegral effects testlight water reactorpressurized water reactorPCT peak cladding temperatureRELAPresponse surfacebayesian statisticswilks method formulaNRCuncertainty quantificationsensitivity analysisthermal hydraulic safety analysisLight water reactors -- Safety measures -- Mathematical modelsWater cooled reactors -- Loss of coolant -- Mathematical modelsLight water reactors -- Risk assessmentNuclear power plants -- Thermodynamics -- Mathematical modelsThe 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 Uncertainty (BEPU) method using a modernized version of the Code-Scaling, Applicability, and Uncertainty (CSAU) methodology has been applied to more accurately predict the safety margins of the Oregon State University Advanced Plant Experiment (APEX) facility experiencing a Loss-of-Feedwater Accident (LOFA). The statistical advantages of the Bayesian paradigm of probability was utilized to incorporate prior knowledge when determining the analysis required to justify the safety margins. RELAP5 Mod 3.3 was used to accurately predict the thermal-hydraulics of a primary Feed-and-Bleed response to the accident using assumptions to accompany the lumped-parameter calculation approach. A novel coupling of thermal-hydraulic and statistical software was accomplished using the Symbolic Nuclear Analysis Package (SNAP). Uncertainty in Peak Cladding Temperature (PCT) was calculated at the 95/95 probability/confidence levels under a series of four separate sensitivity studies.Graduation date: 2013Wu, Qiao2013-03-25T21:17:08Z2013-03-25T21:17:08Z2013-03-052013-03-05Thesis/Dissertationhttp://hdl.handle.net/1957/37872en_US
collection	NDLTD
language	en_US
sources	NDLTD
topic	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
spellingShingle	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 Hallee, Brian Todd Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method
description	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 Uncertainty (BEPU) method using a modernized version of the Code-Scaling, Applicability, and Uncertainty (CSAU) methodology has been applied to more accurately predict the safety margins of the Oregon State University Advanced Plant Experiment (APEX) facility experiencing a Loss-of-Feedwater Accident (LOFA). The statistical advantages of the Bayesian paradigm of probability was utilized to incorporate prior knowledge when determining the analysis required to justify the safety margins. RELAP5 Mod 3.3 was used to accurately predict the thermal-hydraulics of a primary Feed-and-Bleed response to the accident using assumptions to accompany the lumped-parameter calculation approach. A novel coupling of thermal-hydraulic and statistical software was accomplished using the Symbolic Nuclear Analysis Package (SNAP). Uncertainty in Peak Cladding Temperature (PCT) was calculated at the 95/95 probability/confidence levels under a series of four separate sensitivity studies. === Graduation date: 2013
author2	Wu, Qiao
author_facet	Wu, Qiao Hallee, Brian Todd
author	Hallee, Brian Todd
author_sort	Hallee, Brian Todd
title	Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method
title_short	Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method
title_full	Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method
title_fullStr	Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method
title_full_unstemmed	Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method
title_sort	feed-and-bleed transient analysis of osu apex facility using the modern code scaling, applicability, and uncertainty method
publishDate	2013
url	http://hdl.handle.net/1957/37872
work_keys_str_mv	AT halleebriantodd feedandbleedtransientanalysisofosuapexfacilityusingthemoderncodescalingapplicabilityanduncertaintymethod
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Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method

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