1. 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): doi: /
Figure Legend:
Schematic of secondary shutdown system (SSS) for 220 MWel PHWRs

2. 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): doi: /
Figure Legend:
Schematic of automatic liquid poison addition system (ALPAS) and gravity addition of boron (GRAB) for 220 MWel PHWRs

3. 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): doi: /
Figure Legend:
Schematic of liquid poison injection system (LPIS) for 220 MWel PHWRs

4. 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): doi: /
Figure Legend:
Schematic of zone control units, shut down system (SDS)-1 and shut down system (SDS)-2 for 540 and 700 MWel PHWRs

5. 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): doi: /
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

6. 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): doi: /
Figure Legend:
Schematic of containment spray system of 700 MWel PHWR

7. 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): doi: /
Figure Legend:
(a) Calandria with support rods and (b) calandria-end shield integral assembly

8. 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): doi: /
Figure Legend:
(a) Fuel handling system and (b) schematic of passive decay heat removal (PDHR) system of 700 MWel PHWR

9. 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): doi: /
Figure Legend:
Schematic of coolant channel and associated moderator of 540 MWel PHWR (axial view)

10. 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): doi: /
Figure Legend:
Flow diagram of accident analysis

11. 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): doi: /
Figure Legend:
Normalized power as function of time for loss of coolant accident (LOCA) benchmark problem

12. 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): doi: /
Figure Legend:
Relative power versus time in loss of regulation accident (LORA) of 540 MWel PHWR

13. 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): doi: /
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)

14. 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): doi: /
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)

15. 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): doi: /
Figure Legend:
Availability and capacity factors [26] (Courtesy NPCIL, India.)

16. 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): doi: /
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]