The document outlines the fundamentals and components of nuclear reactors, detailing various types and their operations, including fission and fusion reactions. It provides specific information on different reactor types, such as Magnox and PWR, their fuel, cladding, coolant, and efficiency metrics. Additionally, it discusses the status of India's nuclear program, including operational reactors and ongoing projects in development.

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