International audienceThe mathematical modelling and evaluation of the nuclear fuel while burning in nuclear reactors is of significant importance if one wants to predict the reactor core behavior and to get assured that the necessary criteria for its safe operation are met. These criteria reflect the maximum fuel temperature, cladding temperature, coolant heating, etc. The computer code that we chose for performance of such analysis is FEMAXI-6 (Japan Atomic Energy Agency). We prepared input-data deck for fuel rods of the type used in Kozloduy NPP and performed predictive calculations for the evaluation of the safety margins. However, for the proper evaluation it is important to know the initial geometrical and material data. These data ar...
This work is based on the benchmark for uncertainty analysis in modelling of light water reactors co...
Over the last decades the importance of fuel-specific processes for safety analysis has grown, due t...
To construct and operate a nuclear research reactor, the licensee is required to obtain the autho...
The mathematical modelling and evaluation of the nuclear fuel while burning in nuclear reactors is o...
Fuel performance analysis can be used to show compliance with regulatory criteria, such as criteria ...
Analysis of the uncertainty quantification related to nuclear safety margins applied to the nuclear ...
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 fuel matrix and the cladding constitute the first barrier against radioactive fission product r...
The fuel matrix and the cladding constitute the first barrier against radioactive fission product re...
The object of research is the design fuel assemblies (FA-A) at nuclear power plants with water-coole...
Current problem of the ensuring reliability of the results of mathematical computer simulation of th...
Accurately predicting the behavior of nuclear fuel performance is essential for the safe and economi...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2014This study was based on...
International audienceIn the framework of OECD/NEA Working Group on Fuel Safety, a RIA fuel-rod-code...
This work is based on the benchmark for uncertainty analysis in modelling of light water reactors co...
Over the last decades the importance of fuel-specific processes for safety analysis has grown, due t...
To construct and operate a nuclear research reactor, the licensee is required to obtain the autho...
The mathematical modelling and evaluation of the nuclear fuel while burning in nuclear reactors is o...
Fuel performance analysis can be used to show compliance with regulatory criteria, such as criteria ...
Analysis of the uncertainty quantification related to nuclear safety margins applied to the nuclear ...
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 fuel matrix and the cladding constitute the first barrier against radioactive fission product r...
The fuel matrix and the cladding constitute the first barrier against radioactive fission product re...
The object of research is the design fuel assemblies (FA-A) at nuclear power plants with water-coole...
Current problem of the ensuring reliability of the results of mathematical computer simulation of th...
Accurately predicting the behavior of nuclear fuel performance is essential for the safe and economi...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2014This study was based on...
International audienceIn the framework of OECD/NEA Working Group on Fuel Safety, a RIA fuel-rod-code...
This work is based on the benchmark for uncertainty analysis in modelling of light water reactors co...
Over the last decades the importance of fuel-specific processes for safety analysis has grown, due t...
To construct and operate a nuclear research reactor, the licensee is required to obtain the autho...