Outline of the Uncertainty Methodology Based on Accuracy Extrapolation

D'Auria, Francesco Saverio; Debrecin, Nenad; Galassi, G. M.

doi:10.13182/nt109-21

Cited by 87 publications

(30 citation statements)

References 6 publications

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“…4. The bases of the methods and the conditions to be fulfilled for its application, including the use of the FFTBM can be found in references [25] and [26 to 29]. The achieved results may be strongly method/user dependent.…”

Section: A Methods For the Uncertainty Quantification: The Ciau Methodsmentioning

confidence: 99%

BEPU Approach in Licensing Framework, Including 3D NK Applications

Petruzzi¹,

Muellner²,

Parisi³

et al. 2010

New Trends in Technologies: Devices, Computer, Communication and Industrial Systems

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Section: A Methods For the Uncertainty Quantification: The Ciau Methodsmentioning

confidence: 99%

BEPU Approach in Licensing Framework, Including 3D NK Applications

Petruzzi¹,

Muellner²,

Parisi³

et al. 2010

New Trends in Technologies: Devices, Computer, Communication and Industrial Systems

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“…Following and considering the CSAU, the Wilks formulation and the UMAE (Uncertainty Methodology based on Accuracy Extrapolation) were proposed, refs. [16] and [17]. The UMS (Uncertainty Method Study) project was launched by the CSNI in 1993 and completed in 1998, ref.…”

Section: -2000mentioning

confidence: 99%

Perspectives in System Thermal-Hydraulics

D'Auria¹

2012

Nuclear Engineering and Technology

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“…The second approach reviewed as the propagation of code calculation output errors, is representatively illustrated by the Uncertainty Method based upon Accuracy Extrapolation 22) (UMAE) 'embedded' into a Code with the capability of Internal Assessment of Uncertainty 23,24) (CIAU) in Fig. 4.…”

Section: Propagation Of Code Calculation Output Errorsmentioning

confidence: 99%

Role of Best Estimate Plus Uncertainty Methods in Major Nuclear Power Plant Modifications

Andrea¹,

Petruzzi²

2010

Journal of Nuclear Science and Technology

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Current industrial trends to increase power production challenge the initial safety design limits of plants, which were evaluated generally using conservative tools and hypotheses. Advanced numerical tools and methods allow demonstrating that safety margins are still respected. These tools are modern fully validated thermal-hydraulic codes, coupled thermal-hydraulic/neutron-kinetic codes, and methodologies that use realistic hypotheses (rather than conservative ones) and estimate the uncertainty. The paper illustrates modern computational tools and approaches for improving plant operation and control and for supporting design modifications on existing nuclear power plants. A survey performed by Joint Research Centre's Institute for Energy is also presented and summarizes the feedback received by several countries of the European Union on the impact of modern Thermal-Hydraulics and Neutron-Kinetics tools on Operational Limits and Conditions and Operating Instructions and Procedures.

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Outline of the Uncertainty Methodology Based on Accuracy Extrapolation

Cited by 87 publications

References 6 publications

BEPU Approach in Licensing Framework, Including 3D NK Applications

BEPU Approach in Licensing Framework, Including 3D NK Applications

Perspectives in System Thermal-Hydraulics

Role of Best Estimate Plus Uncertainty Methods in Major Nuclear Power Plant Modifications

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