International audienceThe safety assessment of Nuclear Power Plants makes use of Thermal-Hydraulic codes for the quantification of the safety margins with respect to upper/lower safety thresholds, when postulated accidental scenarios occur. To explicitly treat uncertainties in the safety margins estimates within the Risk-Informed Safety Margin Characterization (RISMC) framework, we resort to the concept of Dynamic Probabilistic Safety Margin (DPSM). We propose to add to the framework a sensitivity analysis that calculates how much the Thermal-Hydraulic (TH) code inputs affect the DPSM, in support to the selection of the most proper probabilistic safety assessment method to be used for the problem at hand, between static or dynamic methods (...
[EN] The safety verification of nuclear systems can be done by analyzing the outputs of Best-Estimat...
The challenge of Risk-Informed Safety Margin Characterization (RISMC) is to develop a methodology fo...
Probabilistic Risk Assessment (PRA) is an important tool for evaluating risk in nuclear power plants...
International audienceThe safety assessment of Nuclear Power Plants makes use of Thermal-Hydraulic c...
The development of methodologies for Risk-Informed Safety Margin Characterization (RISMC) in presenc...
Thermal-Hydraulic (TH) codes are used to simulate the response of nuclear safety systems under trans...
Probabilistic safety assessment (PSA) based on event trees and fault trees has been widely used in t...
Probabilistic Safety Assessment (PSA) has been widely used to estimate the overall safety of nuclear...
Probabilistic Safety Assessment (PSA) has been widely used to estimate the overall safety of nuclear...
The concept of “margin” has a long history in nuclear licensing and in the codification of good engi...
The purpose of this research is to introduce the technical standard of accident sequence precursor (...
[EN] There is an attempt nowadays to provide a more comprehensive and realistic safety assessment of...
[EN] The safety verification of nuclear systems can be done by analyzing the outputs of Best-Estimat...
The challenge of Risk-Informed Safety Margin Characterization (RISMC) is to develop a methodology fo...
Probabilistic Risk Assessment (PRA) is an important tool for evaluating risk in nuclear power plants...
International audienceThe safety assessment of Nuclear Power Plants makes use of Thermal-Hydraulic c...
The development of methodologies for Risk-Informed Safety Margin Characterization (RISMC) in presenc...
Thermal-Hydraulic (TH) codes are used to simulate the response of nuclear safety systems under trans...
Probabilistic safety assessment (PSA) based on event trees and fault trees has been widely used in t...
Probabilistic Safety Assessment (PSA) has been widely used to estimate the overall safety of nuclear...
Probabilistic Safety Assessment (PSA) has been widely used to estimate the overall safety of nuclear...
The concept of “margin” has a long history in nuclear licensing and in the codification of good engi...
The purpose of this research is to introduce the technical standard of accident sequence precursor (...
[EN] There is an attempt nowadays to provide a more comprehensive and realistic safety assessment of...
[EN] The safety verification of nuclear systems can be done by analyzing the outputs of Best-Estimat...
The challenge of Risk-Informed Safety Margin Characterization (RISMC) is to develop a methodology fo...
Probabilistic Risk Assessment (PRA) is an important tool for evaluating risk in nuclear power plants...