One of the most widely used methods to estimate core damage during a nuclear power plant accident is containment radiation measurement. The evolution of severe accidents is extremely complex, leading to uncertainty in the containment dose rate (CDR). Therefore, it is difficult to accurately determine core damage. This study proposes to conduct uncertainty analysis of CDR for core damage assessment. First, based on source term estimation, the Monte Carlo (MC) and point-kernel integration methods were used to estimate the probability density function of the CDR under different extents of core damage in accident scenarios with late containment failure. Second, the results were verified by comparing the results of both methods. The point-kernel...
An uncertainty propagation methodology based on the Monte Carlo method is applied to PWR nuclear des...
Fuel performance analysis can be used to show compliance with regulatory criteria, such as criteria ...
In fast spectrum nuclear reactors, reactivity is directly related to the capability of the reactor t...
Nowadays, the available radioactive source term analyses in a nuclear power plant are done by so cal...
It is sometimes the case in PRA applications that reported plant-specific failure data are, in fact,...
The Nuclear Regulatory Commission`s (NRC`s) ongoing Accident Sequence Precursor (ASP) program uses p...
textThis research presents the methodologies used to resolve the Nuclear Regulatory Commission Gener...
The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed...
The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed...
This report presents the final results from the Level 1 probabilistic safety assessment (PSA) for th...
The key papers on estimating the uncertainties in nuclear data deal with the influence of these unce...
A suite of methods has been established to quantitatively estimate uncertainties existed in source t...
A method for propagating the uncertainties in the prediction of postulated accident consequences was...
A MELCOR model of a boiling water reactor has been developed by Sapienza University of Rome in the f...
[[abstract]]Traditional limit load analysis and fracture mechanics analysis have been applied to eva...
An uncertainty propagation methodology based on the Monte Carlo method is applied to PWR nuclear des...
Fuel performance analysis can be used to show compliance with regulatory criteria, such as criteria ...
In fast spectrum nuclear reactors, reactivity is directly related to the capability of the reactor t...
Nowadays, the available radioactive source term analyses in a nuclear power plant are done by so cal...
It is sometimes the case in PRA applications that reported plant-specific failure data are, in fact,...
The Nuclear Regulatory Commission`s (NRC`s) ongoing Accident Sequence Precursor (ASP) program uses p...
textThis research presents the methodologies used to resolve the Nuclear Regulatory Commission Gener...
The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed...
The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed...
This report presents the final results from the Level 1 probabilistic safety assessment (PSA) for th...
The key papers on estimating the uncertainties in nuclear data deal with the influence of these unce...
A suite of methods has been established to quantitatively estimate uncertainties existed in source t...
A method for propagating the uncertainties in the prediction of postulated accident consequences was...
A MELCOR model of a boiling water reactor has been developed by Sapienza University of Rome in the f...
[[abstract]]Traditional limit load analysis and fracture mechanics analysis have been applied to eva...
An uncertainty propagation methodology based on the Monte Carlo method is applied to PWR nuclear des...
Fuel performance analysis can be used to show compliance with regulatory criteria, such as criteria ...
In fast spectrum nuclear reactors, reactivity is directly related to the capability of the reactor t...