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Global Applications of the ASME Boiler & Pressure Vessel Code
Editor
K. R. Rao
K. R. Rao
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ISBN:
9780791861073
No. of Pages:
500
Publisher:
ASME Press
Publication date:
2016

The Nuclear Power Program in India, at present, is based mainly on a series of Pressurized Heavy Water Reactors (PHWRs). Starting from Rajasthan Atomic Power Station, comprising of two units of 200 MWe Canadian-designed PHWRs in 1973, the program has come a long way with 17 PHWR units (which include two units of 540 MWe PHWRs) in operation and four units of 700 MWe PHWRs under construction. Narora Atomic Power Station commissioned in 1991 marked major indigenization and standardization of PHWR design. The current design plan includes 700 MWe capacity units. The choice of PHWRs in the current stage of India’s nuclear power program is based on long-term objectives to be achieved with the available uranium resources and industrial infrastructure. These reactors use natural uranium as fuel and heavy water as moderator and coolant. The nuclear power stations in India are planned as twin-unit modules, sharing common facilities such as service building, control building, turbine building, spent fuel storage bay, and so on.

16A.1
Introduction
16A.2
Indian PHWR
16A.3
Design of Indian Pressurized Heavy Water Reactor Components
16A.4
Design Philosopy for Reactor Components
16A.5
Seismic Qualification, Leak Before Break, ISI, and Containment Design
16A.6
Organization of Design, Fabrication, Construction, Operation, and ISI of NPPs in India
16A.7
Seismic Re-Evaluation of Older Generation Plants
16A.8
Post Fukushima Upgradations for Operating Stations
16A.9
Summary
16A.10
Acknowledgments
16A.11
References
16B.1
Introduction
16B.2
Future Nuclear Cycle in India
16B.3
International Collaborations and Availability of Materials and Technical Know How
16B.4
Summary
16B.5
Acknowledgements
16B.6
References
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