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

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

“…Hence, it is very essential to make sure what kind of accident would possibly be able to trigger the potential pin disruption. Our previous extensive investigation (Suzuki et al, 2005;Maschek et al, 2010;Haas et al, 2008;Chen et al, 2011Chen et al, , 2010Kriventsev et al, 2014) about ADS is also providing a significant experience for the LBE-cooled MYRRHA-FASTEF critical core current study. As requirement for safety analysis, several transient cases have to be studied in order to investigate and assess the safety potential.…”

Comparative Safety Analysis of Accelerator Driven Subcritical Systems and Critical Nuclear Energy Systems

“…Reference Chen et al [13] analyzed some safety characteristics for a lead-bismuth eutectic (LBE) cooled ADS using the extended SIMMER-III code. In addition, Suzuki et al [14] investigeted the unprotected blockage in a single fuel assembly and severe core-melt accidents with the updated SIMMER-III. The neutronics and thermal-hydraulics coupled simulation program was developed by the FDS team for the design and research of lead or LBE cooled ADS reactors [15], and three typical transient accidents were simulated with NTC code, such as beam trip and transient overpower condition [16].…”

Preliminary simulation of fuel dispersion in a Lead-Bismuth Eutectic (LBE)-cooled research reactor

“…Consequent release of solid fuel fragments in the flowing LBE can occur, which potentially leads to severe recriticality and influence on the heat removal. The reference scenario that might induce core degradation is the blockage of an assembly, while in case of loss of flow and loss of heat sink the possibility of core degradation seems to be unlikely (Liu et al, 2010;Suzuki et al, 2005).…”