Nuclear spent fuel cask full scope simulation using coupled Computational Fluid Dynamics models

Probabilistic safety assessment method for spent nuclear fuel road transportation

(2019) Longlong Tao et al.   ANNALS OF NUCLEAR ENERGY

Methodology for thermal analysis of spent nuclear fuel dry cask using CFD codes

(2019) Julio Benavides et al.   ANNALS OF NUCLEAR ENERGY

Heat transfer enhancement in dry cask storage for nuclear spent fuel using additive high density inert gas

(2019) Hee Sang Yoo et al.   ANNALS OF NUCLEAR ENERGY

Dry cask radiation shielding validation and estimation of cask surface dose rate with MAVRIC during long-term storage

(2019) Yuan Gao et al.   ANNALS OF NUCLEAR ENERGY

A probabilistic assessment of PWR SNF cladding pinching failure considering potential transportation accident conditions

(2019) Elmar Eidelpes et al.   NUCLEAR ENGINEERING AND DESIGN

Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage

(2018) Asko Arkoma et al.   ANNALS OF NUCLEAR ENERGY

Thermal modeling of a vertical dry storage cask for used nuclear fuel

(2016) Jie Li et al.   NUCLEAR ENGINEERING AND DESIGN

Comparisons of prediction methods for peak cladding temperature and effective thermal conductivity in spent fuel assemblies of transportation/storage casks

(2014) Hyungjin Kim et al.   ANNALS OF NUCLEAR ENERGY

NATURAL CONVECTION HEAT TRANSFER CHARACTERISTICS IN A CANISTER WITH HORIZONTAL INSTALLATION OF DUAL PURPOSE CASK FOR SPENT NUCLEAR FUEL

(2014) DONG-GYU LEE et al.   Nuclear Engineering and Technology

Full-scope simulation of a dry storage cask using computational fluid dynamics

(2010) Seung Hun Yoo et al.   NUCLEAR ENGINEERING AND DESIGN

Thermal-fluid flow analysis and demonstration test of a spent fuel storage system

(2009) J.C. Lee et al.   NUCLEAR ENGINEERING AND DESIGN

Dynamic thermal building analysis with CFD – modelling radiation

(2008) M. J. Cook et al.   Journal of Building Performance Simulation