The 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 are available only throu...
The object of research is the design fuel assemblies (FA-A) at nuclear power plants with water-coole...
The evaluation of uncertainty is a necessary supplement to Best Estimate (BE) calculations that are ...
The PHEBUS program is an example of an international cooperative research program providing valuable...
International audienceThe mathematical modelling and evaluation of the nuclear fuel while burning in...
Fuel performance analysis can be used to show compliance with regulatory criteria, such as criteria ...
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...
Analysis of the uncertainty quantification related to nuclear safety margins applied to the nuclear ...
To construct and operate a nuclear research reactor, the licensee is required to obtain the autho...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2014This study was based on...
This work is based on the benchmark for uncertainty analysis in modelling of light water reactors co...
The original approach to nuclear reactor design or safety analyses was to make very conservative mod...
A comprehensive uncertainty analysis in the event of a severe accident in a two-loop pressurized wat...
International audienceIn the framework of OECD/NEA Working Group on Fuel Safety, a RIA fuel-rod-code...
The maximum fuel temperature under accident condition is the most important parameter of inherently ...
The object of research is the design fuel assemblies (FA-A) at nuclear power plants with water-coole...
The evaluation of uncertainty is a necessary supplement to Best Estimate (BE) calculations that are ...
The PHEBUS program is an example of an international cooperative research program providing valuable...
International audienceThe mathematical modelling and evaluation of the nuclear fuel while burning in...
Fuel performance analysis can be used to show compliance with regulatory criteria, such as criteria ...
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...
Analysis of the uncertainty quantification related to nuclear safety margins applied to the nuclear ...
To construct and operate a nuclear research reactor, the licensee is required to obtain the autho...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2014This study was based on...
This work is based on the benchmark for uncertainty analysis in modelling of light water reactors co...
The original approach to nuclear reactor design or safety analyses was to make very conservative mod...
A comprehensive uncertainty analysis in the event of a severe accident in a two-loop pressurized wat...
International audienceIn the framework of OECD/NEA Working Group on Fuel Safety, a RIA fuel-rod-code...
The maximum fuel temperature under accident condition is the most important parameter of inherently ...
The object of research is the design fuel assemblies (FA-A) at nuclear power plants with water-coole...
The evaluation of uncertainty is a necessary supplement to Best Estimate (BE) calculations that are ...
The PHEBUS program is an example of an international cooperative research program providing valuable...