Validation of codes for modeling and simulation of nuclear power plants: A review

K Moshkbar-Bakhshayesh, S Mohtashami - Nuclear Engineering and …, 2024 - Elsevier
The validation process is done to ensure the performance of nuclear codes compared to
experimental results and to determine the degree of reliability of codes output. The …

Improving PWR core simulations by Monte Carlo uncertainty analysis and Bayesian inference

E Castro, C Ahnert, O Buss, N Garcia-Herranz… - Annals of Nuclear …, 2016 - Elsevier
Abstract The Monte Carlo-based Bayesian inference model MOCABA is applied to the
prediction of reactor operation parameters of a PWR nuclear power plant. In this non …

[HTML][HTML] Nuclear data uncertainties for core parameters based on Swiss BWR operated cycles

D Rochman, A Dokhane, A Vasiliev, H Ferroukhi… - Annals of Nuclear …, 2020 - Elsevier
The effects of the nuclear data uncertainties are quantified for specific core parameters from
a real Boiling Water Reactor operated over 25 consecutive cycles. Nominal calculations are …

Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics

D Rochman, A Dokhane, A Vasiliev… - … Physical Journal Plus, 2020 - epjplus.epj.org
The effect of nuclear data (fission yields, cross sections and emitted spectra) is quantified for
spent nuclear fuel assemblies from a realistic boiling water reactor operated over 25 cycles …

[图书][B] Incertitudes et ajustements de données nucléaires au moyen de méthodes déterministes, probabilistes et de mesures effectuées sur des réacteurs à eau sous …

V Salino - 2022 - search.proquest.com
La sûreté des réacteurs nucléaires repose en partie sur des prédictions issues de
simulations numériques. Leurs incertitudes doivent donc être évaluées. En neutronique, ces …

Uncertainty propagation from n+ 56Fe nuclear reaction model parameters to neutron multiplication factor

S Chen, E Vandermeersch, P Tamagno… - Annals of Nuclear …, 2021 - Elsevier
Nuclear data are the main uncertainty sources for modern neutron transport calculations.
However, complete correlation matrices among different nuclear data are not presented in …

Uncertainty quantification of the fast flux calculation for a PWR vessel

L Clouvel - 2019 - theses.hal.science
The vessel neutron irradiation, which cannot be replaced, is one of the limiting factors for
pressurized water reactor (PWR) lifetime. Surveillance programmes are therefore necessary …

Fission yields and cross section uncertainty propagation in Boltzmann/Bateman coupled problems: global and local parameters analysis with a focus on MTR

T Frosio, T Bonaccorsi, P Blaise - Annals of Nuclear Energy, 2016 - Elsevier
In a previous paper, a method was investigated to calculate sensitivity coefficients in
coupled Boltzmann/Bateman problem for nuclear data (ND) uncertainties propagation on …

Recent advances in accurate neutronic calculation of GEN-3 LWR reactors

A Santamarina, D Bernard, P Blaise, P Leconte… - Annals of Nuclear …, 2016 - Elsevier
Abstract New French GEN-III reactors are characterized by an improved safety (core catcher
for corium, stainless-steel neutron reflector to minimize vessel embrittlement, permanent in …

Re-estimation of nuclear data and reliable covariances using integral experiments. application to jeff3 library.

A Santamarina, D Bernard - … Methods Applied to Nuclear Science and …, 2017 - hal.science
Differential measurements of Nuclear Data (ND) are not enough accurate in order to meet
the target-accuracy required by reactor design calculation. Moreover, the uncertainties …