Typical thermal hydraulics problems involve the process of heat transfer from structural material to the coolant, coolant flow and interaction of these processes in nuclear reactor or any other chemical reactors.
Analysis of Operational Transients in Nuclear Power Plant and Non-Nuclear Systems
PMD-ACRi team members have been actively involved in the analysis of operational transients in nuclear reactor systems, non-nuclear systems and the balance of plant equipment. We use thermal-hydraulics software such as RELAP5, COBRA, etc., for the transient analysis of these systems. Our experts have decades of operating experience in using these system software. We also utilize sub-system specific software such as MELCOR, etc., to enhance the confidence in the results from such system codes.
Typical problems include:
- Operational Transients-Anticipated Transients without SCRAM
- Containment Transient analysis
- Turbine Transient such as turbine trip
- Steam Generator Transients
- Loss of off-site power
- Loss of feed water
- Separate Effects Core Modelling
- Coupled behavior of the reactor coolant system and the core
- Multi-component and two-phase flow simulation
- Hydraulic assessment of pipelines, safety tanks and safety equipment
- Thermal-hydraulic analysis of chemical reactor
- Thermal behavior of flow lines with consideration of insulation and heating
- Transients analysis of multi-component system
- Safety analysis of two phase flow system
Loss of Coolant Accident (LOCA) Analysis
PMD-ACRi has been involved in carrying out safety system studies for small and large postulated breaks in the primary coolant circuit. Our team members have vast experience in using thermal-hydraulic codes to determine availability and uncertainty in operation of safety system.
LOCA Analysis includes:
- Uncertainty analysis in large break and small break LOCA
- Uncertainty analysis in ECCS system
- Break analysis in steam line and instrumentation line
- Steam generator tube rupture
- Control system performance
We have considerable experience with RELAP5.