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Keywords: uncertainty
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Proceedings Papers

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A103, July 29–August 2, 2013
Paper No: ICONE21-16570
... The uncertainty propagation is an important segment of quantitative uncertainty analysis for complex computational codes (e.g., RELAP5 thermal-hydraulics) computations. Different sampling techniques, dependencies between uncertainty sources, and accurate inference on results are among the issues...
Proceedings Papers

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A041, July 29–August 2, 2013
Paper No: ICONE21-16138
... exchanger is 3.53g which has the inherent randomness about the median and the uncertainty in the median value, respectively, 0.36 and 0.47, and the high confidence low probabilistic failure (HCLPF) capacity is 0.9g, so the air heat exchanger has a better seismic capacity. Seismic Fragility Analysis...
Proceedings Papers

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A011, July 29–August 2, 2013
Paper No: ICONE21-15299
... The conservatism was introduced in the probabilistic safety analysis (PSA) while successes criteria for the event tree were determined. The conservatism has strong relation with the uncertainty but independent with the uncertainty, and the conservatism could significantly influence the CDF...
Proceedings Papers

Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 843-852, July 12–16, 2009
Paper No: ICONE17-76056
... organizations. The computer code user represents a source of uncertainty that can influence the results of system code calculations. This influence is commonly known as the ‘user effect’ and stems from the limitations embedded in the codes as well as from the limited capability of the analysts to use the codes...
Proceedings Papers

Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 405-413, July 12–16, 2009
Paper No: ICONE17-75463
... 23 02 2010 With revising the ECCS licensing rules in 1989, USNRC has allowed the use of “best estimate” thermal-hydraulics computer codes (such as RELAP5 and TRAC) with the requirement that uncertainty analysis accompany the results. Several methodologies have been developed for...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 163-170, April 14–18, 2002
Paper No: ICONE10-22135
... CIAU code Relap5/Mod3.2 code uncertainty accident analysis The Code with - the capability of - Internal Assessment of Uncertainty (CIAU) is a tool proposed by the “Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione (DIMNP)” of the University of Pisa. Other Institutions...
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 305-312, April 25–29, 2004
Paper No: ICONE12-49301
... Vessel failure safety injection structural reliability uncertainty FORM probabilistic mechanics The structural integrity assessment of a nuclear Reactor Pressure Vessel (RPV) during accidental conditions such as loss-of-coolant accident (LOCA) is a major safety concern. Besides...
Proceedings Papers

Proc. ASME. ICONE14, Volume 2: Thermal Hydraulics, 149-158, July 17–20, 2006
Paper No: ICONE14-89184
... Uncertainty sensitivity best-estimate LOFT L2-5 This paper is aimed at describing results of the first part of the BEMUSE ( B est E stimate M ethods – U ncertainty and S ensitivity E valuation) programme. The purpose of BEMUSE is the comparison of best-estimate calculations...
Proceedings Papers

Proc. ASME. ICONE14, Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum, 433-442, July 17–20, 2006
Paper No: ICONE14-89902
... User effect Training Uncertainty best-estimate Thermal-hydraulic system computer codes are extensively used worldwide for analysis of nuclear facilities by utilities, regulatory bodies, nuclear power plant designers and vendors, nuclear fuel companies, research organizations, consulting...