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Comparison of ENDF/B-VII.1 and JEFF-3.2 in VVER-1000 operational data calculation

Delayed neutron library analysis using dynamic control rod calibration method based on results from the VR-1 reactor experiment and Serpent transient calculation

Study of reflection properties of silica sand

Validation of the neutron lead transport for fusion applications

Simulation of criticality of spent nuclear fuel pool by Monte Carlo method

Analysis of the Dosimetry Cross Sections Measurements up to 35 MeV with a (7)Li(p, xn) Quasi-monoenergetic Neutron Source

(237)Np(n,f) Cross Section: New Data and Present Status

Past, Present and Future of the n_TOF Facility at CERN

High-energy Neutron-induced Fission Cross Sections of Natural Lead and Bismuth-209

Neutron measurements for advanced nuclear systems: The n_TOF project at CERN