G-MET Technologies proposes to perform safety calculations for water reactor cooling circuits. Our engineers have a strong experience of CATHARE2 (Code for Analysis of THermalhydraulics during an Accident of Reactor and Safety Evaluation). As such we perform numerical simulations applied to reactor safety and are qualified to simulate and model accidental (or incidental) transients on nuclear reactors (PWR, experimental reactors) such as for example: LOCA (Loss of Coolant Accident – small breach, large breach), Rupture of Piping Steam Generator, Rupture of Steam Piping, LOFA (Loss Of Flow Accident), overpowering etc …
Our engineers have in-depth knowledge of the calculation code and correlations implemented in order to offer a detailed analysis of the physics involved, especially during complex LOCA transient. We bring our expertise to the drafting of safety cases.
Examples of studies involving Thermohydraulics and Safety of Nuclear Reactors
- Writing of data set and CATHARE2 modeling of the cooling loop (exchangers, piping, valves, nuclear fuel ..).
- Definition of appropriate calculation methodologies. Choice of calculation hypotheses and conservatism analysis.
- Physical analysis of the LOCA transient behavior. Calculations of sensitivity on several input parameters.
- Modeling of an accident involving the fall of RJH fuel element in the reactor pool in order to calculate the melting times of the fuel plates.
- Calculation of transients under different degrees of conservatism. Proposition of best-estimate calculation methodologies.
- Conservative evaluation of CATHARE2 for this type of transient.
- Modeling the circuit and writing the CATHARE2 dataset from CAD geometry.
- Calculating operating states.
- Transient calculation and sensitivity analysis.