A brief idea of Nuclear Power Plant has been given by Mr. Anupam Singh, PG Scholar, Department of Electrical and Instrumentation. SLIET Longowal

1. NUCLEAR REACTORS
PRESENTED BY:
ANUPAM SINGH
K GOURI SHANKAR

2. CONTENTS
 INTRODUCTION
 NUCLEAR REACTION
 NUCLEAR REACTOR
 NUCLEAR REACTOR COMPONENTS
 TYPES OF NUCLEAR REACTORS
 GENERATIONS OF NUCLEAR REACTORS
 NUCLEAR REACTORS IN INDIA

3. NUCLEAR REACTION
 A process in which the
structure and energy
content of an atomic
nucleus is changed by
interaction with
another nucleus or
particle .

4. FISSION REACTION

5. FUSION REACTION

6. NUCLEAR REACTOR

7. NEUCLEAR REACTOR-MAIN PARTS
 REACTOR VESSEL
 REACTOR CORE
 FUEL
 MODERATOR
 CONTROL RODS
 COOLANT
 REFLECTORS
 SHIELDING

8. TYPES OF NUCLEAR REACTOR
 MAGNOX(BASIC GAS COOLED
REACTOR)
 AGR(ADVANCED GAS COOLED
REACTORS)
 PWR(PRESSURISED WATER REACTOR)
 BWR(BOILING WATER REACTOR)
 FBR(FAST BREEDER REACTOR)
 CANDU(PRESSURISED HEAVY WATER
REACTOR)
 RBMK(WATER COOLED GRAPHITE

9. MAGNOX REACTOR
 FUEL-0.7% (natural uranium metal) &
magnesium alloy cladding.
 MODERATOR- Graphite
 COOLANT-Carbon Dioxide
 Outlet Temperature-360 degree Celsius
 Pressure-300psia
 Efficiency-31%

10. MAGNOX

11. AGR REACTOR
 FUEL-uranium dioxide enriched to 2.3% natural uranium.
 CLADDING- Stainless steel cladding.
 MODERATOR- Graphite
 COOLANT-Carbon Dioxide
 Outlet Temperature- 650 degree celsius
 Pressure- 600psia
 Efficiency- 42%

12. AGR

13. PWR REACTOR
 FUEL-uranium dioxide enriched to 3.2% natural
uranium.
 CLADDING- Zirconium alloy cladding.
 MODERATOR- light water
 COOLANT- light water
 Outlet Temperature- 317 degree celsius
 Pressure- 2235psia
 Efficiency- 32%

14. PWR

15. FAST BREEDER REACTOR
 FUEL-NATURAL URANIUM
 MODERATOR-NONE
 COOLANT-LIQUID SODIUM
 PLUTONIUM IS PRODUCED DURING NUCLEAR
REACTION

16. FBR

17. BWR REACTOR
 FUEL-uranium dioxide enriched to 2.4% natural uranium.
 CLADDING- Zirconium alloy cladding.
 MODERATOR- Light Water
 COOLANT- Light Water
 Outlet Temperature- 286 degree celsius
 Pressure- 1050psia
 Efficiency- 32%

18. BWR

19. CANDU REACTOR
 FUEL-Un- enriched uranium dioxide to 0.7% natural
uranium.
 CLADDING- Zirconium Alloy cladding.
 MODERATOR- heavy water
 COOLANT- heavy Water
 Outlet Temperature- 305 degree celsius
 Pressure- 1285psia
 Efficiency- 30%

20. CANDU
(CANADIAN DEUTERIUM URANIUM)

21. RBMK REACTOR
 FUEL- uranium dioxide enriched to 1.8 %
natural uranium.
 CLADDING- Zirconium Alloy cladding.
 MODERATOR- Graphite
 COOLANT- Light Water
 Outlet Temperature- 284
 Pressure- 1000psia
 Efficiency- 31%

22. RBMK
(LIGHT WATER GRAPHITE REACTOR)

23. REACTOR GENERATIONS
 Gen I
 Prototypes in 50’s & 60’s
 Gen II
 70’s & 80’s
 Today’s Operational
Reactors
 BWR, PWR, CANDU, …
 Gen III
 ABWR, APWR
 Approved 90’s
 Some Built around the World
 Gen III+
 Current Advanced Designs in
the Approval Process
 Pebble Bed Reactor
 Gen IV
 Deploy in 2030
 Economical
 Safe
 Minimize Waste
 Reduce Proliferation

24. NUCLEAR PROGRAM: PRESENT STATUS IN INDIA
 18 PHWR & 2 BWR now under operation
 4 PHWR and 2 LWR under commission
 6730 MW generation & 4300 MW under
commission
 Successful experiments with Fast Breeder Test
Reactor (FBTR)
 Prototype Fast Breeder Reactor (PFBR) for
500MWe under construction
 Advanced Heavy Water Reactor (AHWR) using
(Pu-Th) for 300MWe: advanced stage of design
approval; construction soon to begin.

25. RESEARCH REACTORS IN INDIA
 Bhabha Atomic Research Center (BARC) – Trombay
 Apsara reactor – 1 MWT, pool type, light water moderated, enriched
uranium fuel supplied by France
 CIRUS reactor – 40 MWT, supplied by Canada, heavy water
moderated, uses natural uranium fuel
 Dhruva reactor – 100 MWT, heavy water moderated, uses natural
uranium fuel
 Indira Gandhi for Atomic Research Center (IGCAR)–
Kalpakkam
 PFBR – 500MWe Sodium cooled fast breeder nuclear reactor under
construction. Expected completion 2013.
 FBTR – 40 MWT Fast Breeder Test Reactor, uses mixed (plutonium
and uranium) carbide fuel
 KAMINI –30 kWT, uses U-233 fuel

26. THANK YOU