Sensitivity and uncertainty analysis of effective multiplication factor of KRITZ-1 benchmark using ENDF/B-VIII.0 and JEFF3-3 nuclear data libraries

Eigenvalue sensitivity and nuclear data uncertainty analysis for the Moroccan TRIGA Mark II research reactor using SCALE6.2 and MCNP6.2

(2021) H. Ziani et al.   NUCLEAR ENGINEERING AND DESIGN

Nuclear-data adjustment based on the continue-energy cross-section library for the fast reactor

(2020) Chenghui Wan et al.   ANNALS OF NUCLEAR ENERGY

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

(2020) A. J. M. Plompen et al.   EUROPEAN PHYSICAL JOURNAL A

Adjustment of group cross sections by means of integral data (ENDF/-VII.1)

(2019) M. Makhloul et al.   PROGRESS IN NUCLEAR ENERGY

ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data

(2018) D.A. Brown et al.   NUCLEAR DATA SHEETS

Resonance Parameter Adjustment Based on Integral Experiments

(2016) Vladimir Sobes et al.   NUCLEAR SCIENCE AND ENGINEERING

Incorporating sensitivity and uncertainty analysis to a lattice physics code with application to CASMO-4

(2011) Maria Pusa   ANNALS OF NUCLEAR ENERGY

ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data

(2011) M.B. Chadwick et al.   NUCLEAR DATA SHEETS