The impact of nuclear data uncertainties is studied for the reactor power and the reactivity during control rod withdrawal transients with reactivity insertions of 0.5$ and 0.97$, respectively, for a PWR mini-core model. Multi-group cross sections, the multiplicities of both prompt and delayed neutrons, and fission spectra are varied by the application of the random sampling-based method XSUSA with covariance data of SCALE 6.1 supplemented by JENDL-4.0. The varied multi-group data are used by TRITON/NEWT to generate varied 2-group cross sections, which are then applied in neutron-kinetic/thermal-hydraulic calculations with DYN3D-ATHLET. A significant impact on both the reactivity uncertainty and the power uncertainty is observed. Since the ...
Sodium-cooled fast reactor (SFR) technologies have the potential to guarantee energy supply and to r...
In nuclear safety analysis, it is very important to be able to simulate the different transients tha...
The propagation of uncertainties in a PWR fuel rod under steady-state irradiation is analyzed by com...
The paper demonstrates the influence of uncertainties in microscopic nuclear data on the results of ...
AbstractThis paper presents a study of the influence of the uncertainty in the macroscopic neutronic...
In nuclear safety analysis, it is very important to be able to simulate the different transients tha...
AbstractThis paper presents a study of the influence of the uncertainty in the macroscopic neutronic...
The Best Estimate analysis consists of a coupled thermal-hydraulic and neutronic description of the ...
This paper presents a nuclear data sensitivity and uncertainty analysis of the effective delayed neu...
This paper presents a nuclear data sensitivity and uncertainty analysis of the effective delayed neu...
This paper presents a nuclear data sensitivity and uncertainty analysis of the effective delayed neu...
The deterministic modeling of LWRs begins with the computation of energy‐collapsed and homogenizedma...
Nuclear data sensitivity analysis and uncertainty propagation have been extensively applied to nucle...
Nuclear data sensitivity analysis and uncertainty propagation have been extensively applied to nucle...
In this study, the Best Estimate Plus Uncertainty (BEPU) approach is developed for the systematic qu...
Sodium-cooled fast reactor (SFR) technologies have the potential to guarantee energy supply and to r...
In nuclear safety analysis, it is very important to be able to simulate the different transients tha...
The propagation of uncertainties in a PWR fuel rod under steady-state irradiation is analyzed by com...
The paper demonstrates the influence of uncertainties in microscopic nuclear data on the results of ...
AbstractThis paper presents a study of the influence of the uncertainty in the macroscopic neutronic...
In nuclear safety analysis, it is very important to be able to simulate the different transients tha...
AbstractThis paper presents a study of the influence of the uncertainty in the macroscopic neutronic...
The Best Estimate analysis consists of a coupled thermal-hydraulic and neutronic description of the ...
This paper presents a nuclear data sensitivity and uncertainty analysis of the effective delayed neu...
This paper presents a nuclear data sensitivity and uncertainty analysis of the effective delayed neu...
This paper presents a nuclear data sensitivity and uncertainty analysis of the effective delayed neu...
The deterministic modeling of LWRs begins with the computation of energy‐collapsed and homogenizedma...
Nuclear data sensitivity analysis and uncertainty propagation have been extensively applied to nucle...
Nuclear data sensitivity analysis and uncertainty propagation have been extensively applied to nucle...
In this study, the Best Estimate Plus Uncertainty (BEPU) approach is developed for the systematic qu...
Sodium-cooled fast reactor (SFR) technologies have the potential to guarantee energy supply and to r...
In nuclear safety analysis, it is very important to be able to simulate the different transients tha...
The propagation of uncertainties in a PWR fuel rod under steady-state irradiation is analyzed by com...