NPCIL Tarapur R&D Centre, Maharashtra

The Nuclear Power Corporation of India Limited (NPCIL) is establishing the Primary Coolant Pump Test Facility (PCPTF) at its Tarapur R&D Centre as part of India’s strategic nuclear power development program. PCPTF is a highly specialized testing and qualification facility created to support the design validation, performance evaluation, and qualification of indigenously manufactured Primary Coolant Pumps (PCPs) intended for future 700 MWe Pressurised Heavy Water Reactors (PHWRs).

Primary Coolant Pumps are among the most critical safety-classified rotating equipment in a nuclear reactor, responsible for circulating reactor coolant under extreme pressure, temperature, and radiation conditions. The PCPTF at Tarapur enables full-scale testing of these pumps under simulated reactor operating conditions, ensuring compliance with stringent nuclear safety, reliability, and regulatory requirements before deployment in operating nuclear power plants.

The PCPTF is engineered to replicate actual reactor coolant system conditions, including high flow rates, elevated pressures, and thermal loads representative of nuclear reactor operation. The facility allows comprehensive evaluation of pump hydraulics, vibration characteristics, mechanical integrity, and long-term operational stability. Such testing is essential to meet the highest nuclear safety classifications and regulatory expectations.

From a national capability perspective, the PCPTF represents a major milestone in India’s nuclear self-reliance initiative. By enabling indigenous design qualification of Primary Coolant Pumps, the facility reduces dependency on imports while strengthening domestic nuclear manufacturing expertise. This reference highlights advanced engineering capability in supporting nuclear R&D infrastructure and safety-critical nuclear systems.