The maximum fuel temperature under accident condition is the most important parameter of inherently safe characteristics of HTR-PM, and the DLOFC accident may lead to a peak accident fuel temperature. And there are a variety of uncertainty sources in the maximum fuel temperature calculations, and thus the contributions of these uncertainty sources to the final calculated maximum fuel temperature should be quantified to check whether the peak value exceed the technological limit of 1620°C or not. Eight uncertainty input parameters are selected for inclusion in this uncertainty study, and their associated 2 standard deviation uncertainties and probability density functions are specified. Then, the DLOFC thermal analyses and uncertainty analys...
This report documents an effort to quantify the uncertainty of the calculated temperature data for t...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2014This study was based on...
The High Temperature Reactor (HTR) is one of the six Generation IV advanced reactor designs. HTRs ha...
The Very High Temperature Reactor Methods Development group at the Idaho National Laboratory identif...
The mathematical modelling and evaluation of the nuclear fuel while burning in nuclear reactors is o...
The continued development of High Temperature Gas Cooled Reactors (HTGRs) requires verification of d...
Thesis (M.Ing. (Mechanical Engineering))--North-West University, Potchefstroom Campus, 2007.The worl...
The fulfillment of the safety analysis acceptance criteria is usually evaluated by separate hot chan...
In this study, the Best Estimate Plus Uncertainty (BEPU) approach is developed for the systematic qu...
The PHEBUS program is an example of an international cooperative research program providing valuable...
The IAEA Coordinated Research Project on high temperature gas-cooled reactor uncertainty analysis in...
Fuel performance analysis can be used to show compliance with regulatory criteria, such as criteria ...
In this study, uncertainty and sensitivity analyses were performed with MELCOR 2.2.18 to study the h...
The potential impact of nuclear data uncertainties on a number of performance parameters (core and f...
Linear propagatlon of errors evaluates modeling uncertainty by approximating a function of interest ...
This report documents an effort to quantify the uncertainty of the calculated temperature data for t...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2014This study was based on...
The High Temperature Reactor (HTR) is one of the six Generation IV advanced reactor designs. HTRs ha...
The Very High Temperature Reactor Methods Development group at the Idaho National Laboratory identif...
The mathematical modelling and evaluation of the nuclear fuel while burning in nuclear reactors is o...
The continued development of High Temperature Gas Cooled Reactors (HTGRs) requires verification of d...
Thesis (M.Ing. (Mechanical Engineering))--North-West University, Potchefstroom Campus, 2007.The worl...
The fulfillment of the safety analysis acceptance criteria is usually evaluated by separate hot chan...
In this study, the Best Estimate Plus Uncertainty (BEPU) approach is developed for the systematic qu...
The PHEBUS program is an example of an international cooperative research program providing valuable...
The IAEA Coordinated Research Project on high temperature gas-cooled reactor uncertainty analysis in...
Fuel performance analysis can be used to show compliance with regulatory criteria, such as criteria ...
In this study, uncertainty and sensitivity analyses were performed with MELCOR 2.2.18 to study the h...
The potential impact of nuclear data uncertainties on a number of performance parameters (core and f...
Linear propagatlon of errors evaluates modeling uncertainty by approximating a function of interest ...
This report documents an effort to quantify the uncertainty of the calculated temperature data for t...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2014This study was based on...
The High Temperature Reactor (HTR) is one of the six Generation IV advanced reactor designs. HTRs ha...