RESEARCH AND DEVELOPMENT
- Analytical studies which have permitted the inclusion of the simplified static load coefficient method into the ASME Boiler and Pressure Vessel Code for piping;
- Application of knowledge regarding the structural-mechanical design and safety analysis of the PWR, BWR, CANDU, and especially the VVER type nuclear reactor plants;
- Research, development, safety analysis report preparation, and regulatory and licensing assistance;
- Development of database systems and qualification documentation management methods for nuclear power plant equipment.