Studies of fuel dispersion after pin failure: Analysis of assumed blockage accidents for the MYRRHA–FASTEF critical core

MYRRHA – A multi-purpose fast spectrum research reactor

Hamid Aı̈t Abderrahim, P. Baeten, Didier De Bruyn et al. · Energy Conversion and Management · 2012 · 210 citations

Engineering, Nuclear Engineering, Physics +12

SIMMER-III : An advanced computer program for LMFBR severe accident analysis

Shunsuke KONDO · 1992 · 67 citations

Engineering, Risk Management, Safety Engineering +2

Transient analyses for accelerator driven system PDS-XADS using the extended SIMMER-III code

Tohru Suzuki, Xue-Nong Chen, A. Rineiski et al. · Nuclear Engineering and Design · 2005 · 50 citations

Engineering, Computer Engineering, Computer Science +13

Thermodynamic properties and equations of state for fast reactor safety analysis

Koji Morita, E.A. Fischer · Nuclear Engineering and Design · 1998 · 49 citations

Engineering, Nuclear Engineering, Physics +14

The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)

M. Sarotto, D. Castelliti, Rafaël Fernandez et al. · Nuclear Engineering and Design · 2013 · 37 citations

Engineering, Computer Engineering, Computer Systems +10