Quantifying fission product yield uncertainty contribution to reactor burnup calculation is an important aspect of pebble-bed High Temperature Gas-cooled Reactor (pebble-bed HTGR) uncertainty analysis. In this work, uncertainty propagation of fission product yield to pebble-bed HTGR burnup calculation is conducted. Uncertainty of fission product yields from four fissile isotopes, namely 233U, 235U, 239Pu and 241Pu, are considered. The stochastic sampling-based uncertainty analysis method is adopted and fission product yield covariance matrices are estimated from ENDF/B-VII.1. The covariance matrix for each fissile actinide is estimated based on the Bayesian method and fission product yields are assigned with log-normal distribution in the s...
An uncertainty analysis was performed for the tritium breeding ratio (TBR) of a fusion power plant o...
This report describes a novel approach developed at the Oak Ridge National Laboratory (ORNL) for the...
The work presented in this paper deals with bias and uncertainty quantification on nuclear fuel inve...
Multi-pass refueling scheme is a highlighted feature of pebble bed HTGR which spatially mixes the bu...
Uncertainty contribution on manufacturing factors and nuclear cross section in pebble bed nuclear fu...
Fission yield uncertainties and correlations should be considered in the uncertainty quantification ...
A considerable support has been given in URANIE utilization by the research group of DEN/DER/SPRC/LE...
In the present work, we analyze how fission yields uncertainties can be propagated in a burn-up calc...
The key papers on estimating the uncertainties in nuclear data deal with the influence of these unce...
The passive gamma spectroscopy (PGS) is a useful technique to extract information on spent nuclear f...
Knowledge of spent nuclear fuel (SNF) source term (decay heat, reactivity, nuclide inventory and oth...
Nuclear data-induced uncertainties of infinite neutron multiplication factors (k) during fuel deplet...
An analysis of a pyroprocessing safeguards methodology employing the Pu-to-244Cm ratio is presented....
Fission product yields (FY) are fundamental nuclear data for several applications, including decay h...
Knowledge of spent nuclear fuel (SNF) source term, for example decay heat, reactivity and nuclide in...
An uncertainty analysis was performed for the tritium breeding ratio (TBR) of a fusion power plant o...
This report describes a novel approach developed at the Oak Ridge National Laboratory (ORNL) for the...
The work presented in this paper deals with bias and uncertainty quantification on nuclear fuel inve...
Multi-pass refueling scheme is a highlighted feature of pebble bed HTGR which spatially mixes the bu...
Uncertainty contribution on manufacturing factors and nuclear cross section in pebble bed nuclear fu...
Fission yield uncertainties and correlations should be considered in the uncertainty quantification ...
A considerable support has been given in URANIE utilization by the research group of DEN/DER/SPRC/LE...
In the present work, we analyze how fission yields uncertainties can be propagated in a burn-up calc...
The key papers on estimating the uncertainties in nuclear data deal with the influence of these unce...
The passive gamma spectroscopy (PGS) is a useful technique to extract information on spent nuclear f...
Knowledge of spent nuclear fuel (SNF) source term (decay heat, reactivity, nuclide inventory and oth...
Nuclear data-induced uncertainties of infinite neutron multiplication factors (k) during fuel deplet...
An analysis of a pyroprocessing safeguards methodology employing the Pu-to-244Cm ratio is presented....
Fission product yields (FY) are fundamental nuclear data for several applications, including decay h...
Knowledge of spent nuclear fuel (SNF) source term, for example decay heat, reactivity and nuclide in...
An uncertainty analysis was performed for the tritium breeding ratio (TBR) of a fusion power plant o...
This report describes a novel approach developed at the Oak Ridge National Laboratory (ORNL) for the...
The work presented in this paper deals with bias and uncertainty quantification on nuclear fuel inve...