Challenges and progress of uncertainty analysis for the pebble-bed high-temperature gas-cooled reactor

J Guo, Y Wang, H Zhang, M Cui, F Li - Progress in Nuclear Energy, 2021 - Elsevier
There has been increasing demand for uncertainty quantification (UQ) in the nuclear
engineering community. Thus far, most uncertainty analyses have focused on light water …

Nuclear data uncertainties for typical LWR fuel assemblies and a simple reactor core

D Rochman, O Leray, M Hursin, H Ferroukhi… - Nuclear Data …, 2017 - Elsevier
The impact of the current nuclear data library covariances such as in ENDF/B-VII. 1, JEFF-
3.2, JENDL-4.0, SCALE and TENDL, for relevant current reactors is presented in this work …

SCALE capabilities for high temperature gas-cooled reactor analysis

F Bostelmann, C Celik, ML Williams, RJ Ellis… - Annals of Nuclear …, 2020 - Elsevier
The SCALE code system's ability to address stochastic distributions of fuel particles within a
graphite matrix has been revisited in both multigroup (MG) features and continuous-energy …

Nuclear data uncertainty propagation and modeling uncertainty impact evaluation in neutronics core simulation

D Huang, HS Abdel-Khalik - Progress in Nuclear Energy, 2020 - Elsevier
Uncertainty analysis is a critical requirement in reactor simulation as it is used to quantify the
reliability of best-estimate calculation. A comprehensive uncertainty analysis should …

A variance deconvolution estimator for efficient uncertainty quantification in Monte Carlo radiation transport applications

KB Clements, G Geraci, AJ Olson, TS Palmer - Journal of Quantitative …, 2024 - Elsevier
Monte Carlo simulations are at the heart of many high-fidelity simulations and analyses for
radiation transport systems. As is the case with any complex computational model, it is …

Decay heat uncertainty for BWR used fuel due to modeling and nuclear data uncertainties

G Ilas, H Liljenfeldt - Nuclear Engineering and Design, 2017 - Elsevier
Abstract Characterization of the energy released from radionuclide decay in nuclear fuel
discharged from reactors is essential for the design, safety, and licensing analyses of used …

[HTML][HTML] Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters

B Ebiwonjumi, C Kong, P Zhang, A Cherezov… - Nuclear Engineering and …, 2021 - Elsevier
Uncertainties are calculated for pressurized water reactor (PWR) spent nuclear fuel (SNF)
characteristics. The deterministic code STREAM is currently being used as an SNF analysis …

[HTML][HTML] Nuclear data uncertainty and sensitivity analysis with XSUSA for fuel assembly depletion calculations

W Zwermann, A Aures, L Gallner, V Hannstein… - Nuclear Engineering …, 2014 - Elsevier
Uncertainty and sensitivity analyses with respect to nuclear data are performed with
depletion calculations for BWR and PWR fuel assemblies specified in the framework of the …

Combining simulations and data with deep learning and uncertainty quantification for advanced energy modeling

MI Radaideh, T Kozlowski - International Journal of Energy …, 2019 - Wiley Online Library
A novel and modern framework for energy modeling is developed in this paper with a focus
on nuclear energy modeling and simulation. The framework combines multiphysics …

Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit

IC Gauld, U Mertyurek - Nuclear Engineering and Design, 2019 - Elsevier
Validating boiling water reactor (BWR) spent nuclear fuel inventory calculations is
challenging due to the complexity of BWR assembly designs, the lack of publicly available …