CAFTA software), systematic review of initiating events resulting in activity release and common cause failure (CCF) methodology documentation.
Spent fuel dry storage design and safety analysis.
Operation and reactor start-up support: commissioning, reactor regulating system and fuel management.
CANDU Station Support: Spent Fuel Bay analysis, Tritium Water Storage
Licensing: RD-310 implementation, support with regulatory interactions
Hydrogen: Passive Autocatalytic (Hydrogen) Recombiner (PAR) design and implementation, Hydrogen Analysis (Fukushima)
Safety Analysis Codes and
Consulting specialities include:
Deterministic Safety Analysis: PHTS accident scenarios (CATHENA), physics modeling (WIMS, DRAGON, RFSP, RCCTS), moderator and end-shielding simulations (CATHENA).
Dose and Containment Analysis: thermal-hydraulics, radionuclide transport and retention inside the reactor building, and radionuclide release (GOTHIC, SMART), atmospheric dispersion and doses to the public (ADDAM).
Probabilistic Safety & Risk Analysis: Level 1 and Level 2 PSA analysis, PSA-Based Seismic Margin Assessment, Fault tree modelling and analysis (FTA with