Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: Schematic of secondary shutdown system (SSS) for 220 MWel PHWRs

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: Schematic of automatic liquid poison addition system (ALPAS) and gravity addition of boron (GRAB) for 220 MWel PHWRs

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: Schematic of liquid poison injection system (LPIS) for 220 MWel PHWRs

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: Schematic of zone control units, shut down system (SDS)-1 and shut down system (SDS)-2 for 540 and 700 MWel PHWRs

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: Schematic of containments of (a) RAPS, (b) KAPS, (c) Kaiga standardized 220 MWel PHWR, and (d) Crane putting steam generator through containment opening

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: Schematic of containment spray system of 700 MWel PHWR

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: (a) Calandria with support rods and (b) calandria-end shield integral assembly

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: (a) Fuel handling system and (b) schematic of passive decay heat removal (PDHR) system of 700 MWel PHWR

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: Schematic of coolant channel and associated moderator of 540 MWel PHWR (axial view)

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: Flow diagram of accident analysis

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: Normalized power as function of time for loss of coolant accident (LOCA) benchmark problem

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: Relative power versus time in loss of regulation accident (LORA) of 540 MWel PHWR

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: (a) Emergency power supply scheme in a nuclear power plant and (b) fault tree for emergency power supply system in a nuclear power plant (courtesy P. V. Varde, BARC)

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: (a) Simplified illustration showing event tree approach for accident sequence and core damage frequency (CDF) evaluation for off-site power supply failure scenario and (b) core damage frequency (courtesy P. V. Varde, BARC)

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: Availability and capacity factors [26] (Courtesy NPCIL, India.)

Date of download: 11/7/2017 Copyright © ASME. All rights reserved. From: Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ASME J of Nuclear Rad Sci. 2017;3(2):020902-020902-13. doi:10.1115/1.4035435 Figure Legend: Variation of fissile inventory of U235 and U233 in gm/kg as function of burn-up when 3% enriched UO2 and ThO2 is used in PHWRs [34]