Numerical simulation of a Hypothetical Core Disruptive Accident in a small-scale model of a nuclear reactor

The cova programme for the validation of computer codes for fast reactor containment studies

N. E. Hoskin, M.J. Lancefield · Nuclear Engineering and Design · 1978 · 18 citations

Engineering, Computer Science, Nuclear Engineering +16

Hydrogen combustion loads—plexus calculations

Etienne Studer, P. Galon · Nuclear Engineering and Design · 1997 · 17 citations

Engineering, Chemical Engineering, Mechanical Engineering +11

PLEXUS: A General Computer Code for Explicit Lagrangian Computation

C. Chavant, Andrea V. Hoffmann, P. Verpeaux et al. · NCSU Libraries Repository (North Carolina State University Libraries) · 1979 · 16 citations · Full text

Engineering, Computer Science, Mathematics +12

Comparison of different LMFBR primary containment codes applied to a benchmark problem

A. Benuzzi‐Mounaix · Nuclear Engineering and Design · 1987 · 15 citations

Computing, Computational Engineering, Algorithms +2

Numerical interpretation of the mara 8 experiment simulating a hypothetical core disruptive accident

M. F. Robbe, M. Lepareux, Y. Cariou · Nuclear Engineering and Design · 2003 · 15 citations

Engineering, Civil Engineering, Physics +8