The TENDL library: Hope, reality and future

D Rochman, AJ Koning, JC Sublet… - EPJ web of …, 2017 - epj-conferences.org
The TALYS Evaluated Nuclear Data Library (TENDL) has now 8 releases since 2008.
Considerable experience has been acquired for the production of such general-purpose …

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 …

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 …

[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 …

Uncertainty Quantification for the Doppler Reactivity Feedback Coefficient of MYRRHA

L Fiorito, M Zanetti, F Grimaldi… - Nuclear Science and …, 2024 - Taylor & Francis
Safety analyses of MYRRHA require calculating the reactor temperature feedback
coefficients of reactivity associated with power operation. Within this framework, a significant …

Assessing and improving model fitness in MOCABA data assimilation

A Hoefer, O Buss - Annals of Nuclear Energy, 2021 - Elsevier
A mathematical and computational framework is introduced to assess and improve the
fitness of multivariate distribution models used in combination with the Bayesian data …

[HTML][HTML] McCARD/MIG stochastic sampling calculations for nuclear cross section sensitivity and uncertainty analysis

HJ Park - Nuclear Engineering and Technology, 2022 - Elsevier
In this study, a cross section stochastic sampling (SS) capability is implemented into both the
McCARD continuous energy Monte Carlo code and MIG multiple-correlated data sampling …

NUSS: A tool for propagating multigroup nuclear data covariances in pointwise ACE-formatted nuclear data using stochastic sampling method

T Zhu, A Vasiliev, H Ferroukhi, A Pautz - Annals of Nuclear Energy, 2015 - Elsevier
Stochastic sampling (SS) method for quantifying nuclear data uncertainties is accomplished
by using perturbed nuclear data in routine neutronics calculations and determining the …

Uncertainty comparison between ENDF/B-VIII. 0 and ENDF/B-VII. 1 for fast reactor BN-600 using high-precision sampling method

X Ma, Y Huang, W Qu, F Zhou, X Peng, H Kui… - Annals of Nuclear …, 2021 - Elsevier
A method of using small samples to achieve high-precision related variable sequence
sampling was proposed. This method mainly uses two techniques: Latin hypercube …

On the use of criticality and depletion benchmarks for verification of nuclear data

L Fiorito, P Romojaro, O Cabellos… - Annals of Nuclear …, 2021 - Elsevier
The problem of calculating sensitivity coefficients to nuclear data in burnup problems is
addressed. A non-intrusive method based on the random sampling of nuclear data and on …