Nuclear Engineering and Design

Title Publication Date Language Citations
Development of an efficient and improved core thermal-hydraulics predictive capability for fast reactors: Summary of research and development activities at the North Carolina state University2023/10/01English
Fast reactor thermal hydraulics in the Dutch PIONEER program2023/10/01English
Editorial Board2023/09/01English
Experimental characterization of the flowline of a lithium film formed using an electromagnetic thruster for a RAON prototype charge stripper2023/10/01English
Uncertainty and sensitivity analysis of iodine release in severe accidents of advanced pressurized water reactors based on the Latin Hypercube method and Grey Correlation Coefficients2023/10/01English
Uncertainty quantification of a spent fuel refrigeration pool utilizing a k−ϵ turbulence reduced order model2023/10/01English
Deterministic sampling methods coupled with dynamic coverage factors for uncertainty analyses in MELCOR simulation2023/11/01English
Model of water transfer in concrete and rock based on a single state variable to consider simultaneous positive pressure and drying boundary conditions2023/11/01English
Characterization of the Fast-Neutron Irradiator and the Fast-Flux Tube Irradiation Fixtures at the Pennsylvania State Breazeale Reactor2023/11/01English
Calculation of boron concentration dependent reactivity versus moderator density curve with application on ATWS analysis for Maanshan PWR plant2023/09/01English
A non-invasive measurement approach of boric acid concentration for anticipating reactivity excursion in light water integrated small modular reactors2023/11/01English
A pore pressure model and cracking strength analysis on the UO2 high burnup structure2023/10/01English
Using temperature and flow fields to detect gas leakage from canisters containing spent nuclear fuel: Applications to RAMM-TM2023/10/01English
Experimental study on kinetic oxidation of graphite IG-110 by steam2023/08/01English
Modelling of a passive hydraulic lock concept for the mitigation transfer tubes in a SFR core2023/08/01English
An experimental test for gas pressure measurement within a realistic crack in concrete2023/03/01English
Coregistered positron emission particle tracking (PEPT) and X-ray computed tomography (CT) for engineering flow measurements2023/03/01English
Research on simplification of branches method of accident sequences based on expert knowledge and heuristic optimization algorithm2023/04/01English
Neutronic characteristics of the VVER-1000 fuel assembly with mechanical spectral shift regulationEnglish
‘Muramig’ 400 AMP. CO2 semi-automatic water-cooled arc welding equipment1966/12/01English
CESAR experiment: Sodium boiling during Transient OverPowerEnglish
Research on calcination thermal decomposition process of simulated high-level liquid waste based on two-step vitrificationEnglish
Concept of the polish high temperature gas-cooled reactor HTGR-POLAEnglish
Preface for the “Outcomes and achievements from researches orienting the future in nuclear fission technology: Bulgaria, Hungary and Romania”English
Volume of Fluid simulation of air–water co-current and Counter-current flow with variable density turbulence formulationEnglish
Fragmentation of fuel particles in rolling U3Si2-Al dispersion fuel platesEnglish
Editorial BoardEnglish
Scaling law method for cost estimation of Indonesia’s first HTGR (PeLUIt-40) and its implementation strategyEnglish
Virtual radionuclide laboratory: An e-learning solution for a tailored training eventEnglish
Near regional geology of Pantai Gosong NPP Site, West Kalimantan, Indonesia: Capable fault and geotechnical hazards assessmentEnglish