Review of Early 21st-Century Monte Carlo Perturbation and Sensitivity Techniques for k-Eigenvalue Radiation Transport Calculations

BC Kiedrowski - Nuclear Science and Engineering, 2017 - Taylor & Francis
Abstract Since the 1960s, Monte Carlo methods have been used to compute the effect of
perturbations on system responses and for computing sensitivity coefficients. This review …

A review of the current nuclear data performance assessments in advanced nuclear reactor systems

AA Ryzhkov, GV Tikhomirov, MY Ternovykh - Annals of Nuclear Energy, 2024 - Elsevier
There is a rise in sensitivity and uncertainty analyses with respect to nuclear data, which are
a basis for a neutron transport simulation. The analyses are primarily concerned with the …

Development of a reduced order model for fuel burnup analysis

C Castagna, M Aufiero, S Lorenzi, G Lomonaco… - Energies, 2020 - mdpi.com
Fuel burnup analysis requires a high computational cost for full core calculations, due to the
amount of the information processed for the total reaction rates in many burnup regions …

[HTML][HTML] Preliminary uncertainty and sensitivity analysis of the Molten Salt Fast Reactor steady-state using a Polynomial Chaos Expansion method

M Santanoceto, M Tiberga, Z Perkó, S Dulla… - Annals of Nuclear …, 2021 - Elsevier
In this work, we present the results of a preliminary uncertainty quantification and sensitivity
analysis study of the Molten Salt Fast Reactor (MSFR) behavior at steady-state performed by …

An Adjoint Proper Orthogonal Decomposition method for a neutronics reduced order model

S Lorenzi - Annals of Nuclear Energy, 2018 - Elsevier
This paper deals with the use of Reduced Order Methods for neutronics modelling. This
approach is used whether both accuracy and computational efficiency are required. A very …

Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors

N Abrate, S Dulla, P Ravetto - Annals of Nuclear Energy, 2021 - Elsevier
The design of innovative nuclear fission systems requires a careful evaluation of the
uncertainties affecting the basic input data. Among them, nuclear data are particularly …

Comparison and evaluation of resolved resonance region covariance representations

H Belanger, A Lewis, D Barry - Journal of Nuclear Science and …, 2024 - Taylor & Francis
The covariance matrices for the evaluated resolved resonance region parameters are
typically processed into a grouped covariance representation for use in uncertainty …

A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design

A Aimetta, N Abrate, S Dulla, A Froio - Nuclear Science and …, 2023 - Taylor & Francis
It is widely recognized that the safe and robust design of a nuclear system requires an
uncertainty propagation analysis concerning the various nuclear data used as input …

Correlation in the fast neutron range via integral information

D Rochman, E Bauge, A Vasiliev… - EPJ N-Nuclear Sciences …, 2017 - cea.hal.science
This paper presents a Bayesian approach based on integral experiments to create
correlations which do not appear with differential data. Some quantities such as the fission …

Nuclear data uncertainty propagation for the molten salt fast reactor design

N Abrate, A Aimetta, S Dulla… - Nuclear Science and …, 2023 - Taylor & Francis
The development of new reactor technologies requires careful assessments of the various
sources of epistemic uncertainties. In this work, nuclear data uncertainties featuring the main …