A method for propagating the uncertainties in the prediction of postulated accident consequences was devised. The method uses simplified mathematical models, derived from first principles and detailed deterministic computer model results to describe controlling physical processes in the transport of radioactive material from the plant and resulting population doses and health effects. These simplified models are used in a computationally efficient Monte Carlo error propagation technique. The approach is shown to be useful for uncertainty analysis of core heatup accidents postulated for the High Temperature Gas-Cooled Reactor. In combination with accident frequency predictions, the method provides the complementary cumulative risk curves typ...
The fulfillment of the safety analysis acceptance criteria is usually evaluated by separate hot chan...
Integrated severe accident codes should be capable of simulating not only specific physical phenomen...
The Analytic Hierarchy Process (AHP) has been used to help determine the importance of components an...
The High Temperature Reactor (HTR) is one of the six Generation IV advanced reactor designs. HTRs ha...
Abstract. Reactor safety analyses often utilize a deterministic approach where in addition to perfor...
An uncertainty propagation methodology based on the Monte Carlo method is applied to PWR nuclear des...
An uncertainty propagation methodology based on the Monte Carlo method is applied to PWR nuclear des...
The methods applied or proposed for risk assessment of nuclear reactors are reviewed, particularly w...
The frequency of occurrence of an accident is a key aspect in the risk assessment field. Vari- ables...
The aim of this work is to review different Monte Carlo techniques used to propagate nuclear data un...
One of the most widely used methods to estimate core damage during a nuclear power plant accident is...
The original approach to nuclear reactor design or safety analyses was to make very conservative mod...
The evaluation of uncertainty constitutes the necessary supplement of Best Estimate (BE) calculati...
Transient analyses at Forsmark nuclear power plant are currently performed using realistic computer ...
Two approaches can be distinguished for uncertainty evaluation that are characterized as “propagatio...
The fulfillment of the safety analysis acceptance criteria is usually evaluated by separate hot chan...
Integrated severe accident codes should be capable of simulating not only specific physical phenomen...
The Analytic Hierarchy Process (AHP) has been used to help determine the importance of components an...
The High Temperature Reactor (HTR) is one of the six Generation IV advanced reactor designs. HTRs ha...
Abstract. Reactor safety analyses often utilize a deterministic approach where in addition to perfor...
An uncertainty propagation methodology based on the Monte Carlo method is applied to PWR nuclear des...
An uncertainty propagation methodology based on the Monte Carlo method is applied to PWR nuclear des...
The methods applied or proposed for risk assessment of nuclear reactors are reviewed, particularly w...
The frequency of occurrence of an accident is a key aspect in the risk assessment field. Vari- ables...
The aim of this work is to review different Monte Carlo techniques used to propagate nuclear data un...
One of the most widely used methods to estimate core damage during a nuclear power plant accident is...
The original approach to nuclear reactor design or safety analyses was to make very conservative mod...
The evaluation of uncertainty constitutes the necessary supplement of Best Estimate (BE) calculati...
Transient analyses at Forsmark nuclear power plant are currently performed using realistic computer ...
Two approaches can be distinguished for uncertainty evaluation that are characterized as “propagatio...
The fulfillment of the safety analysis acceptance criteria is usually evaluated by separate hot chan...
Integrated severe accident codes should be capable of simulating not only specific physical phenomen...
The Analytic Hierarchy Process (AHP) has been used to help determine the importance of components an...