โข๏ธ
Module 3 ยท Nuclear Power Plant: Overview
Nuclear power releases a huge amount of energy from a small amount of fissile material via nuclear fission. It is the cheapest non-hydroelectric power source in India and is used as a base load plant (high load factor > 80%).
Einstein's Mass-Energy Equivalence
$$\boxed{E = mc^2} \quad c = 3 \times 10^8\;\text{m/s}$$
Nuclear Fission Reaction
$${}^{235}_{92}\text{U} + {}^{1}_{0}n \rightarrow \text{Fission products} + 2.5\;{}^{1}_{0}n + Q$$
$$Q \approx 200\;\text{MeV per fission}$$
$$1\;\text{MeV} = 1.6 \times 10^{-13}\;\text{J}$$
$$Q_{total} = 200 \times 1.6 \times 10^{-13} = 3.2 \times 10^{-11}\;\text{J/fission}$$
Energy Comparison
$$1\;\text{kg of U-235} \equiv 2.7 \times 10^6\;\text{kg of coal (same energy)}$$
India's Nuclear Status
$$\text{Capacity: } 6{,}780\;\text{MW} = 1.8\%\;\text{of total installed}$$
โข๏ธ Fission & Energy Comparison
โข๏ธ
1 kg U-235
=
โฐ๏ธ
2,700,000 kg Coal
E = mcยฒ CALCULATOR
โ๏ธ
Module 3 ยท Nuclear Power Plant: Components
A nuclear power plant contains the reactor core (fuel rods + moderator), control rods (reaction control), coolant (heat removal), reflector, biological shield, and containment structure.
Moderator โ Slows Neutrons
$$\text{Fast neutron} \xrightarrow{\text{Moderator}} \text{Thermal neutron (slow)}$$
$$\text{Materials: } D_2O\text{ (best)},\;\text{Graphite},\;\text{Beryllium},\;\text{Light water}$$
Control Rods โ Absorb Neutrons
$$\text{Materials: Boron (B), Cadmium (Cd), Hafnium (Hf)}$$
$$k_{eff} = 1:\;\text{Critical (sustained reaction)}$$
$$k_{eff} < 1:\;\text{Sub-critical (reaction dies)}$$
$$k_{eff} > 1:\;\text{Super-critical (runaway โ danger!)}$$
Coolant Heat Removal
$$Q_{coolant} = \dot{m}_c \cdot c_p \cdot (T_{out} - T_{in})$$
$$\text{Types: Light water, Heavy water, Liquid Na, CO}_2\text{, He}$$
Radiation Shielding
$$I = I_0 \cdot e^{-\mu x}$$
$$\text{Where } \mu = \text{attenuation coefficient},\; x = \text{shield thickness}$$
Fuel Rod Cladding
| Material | Advantage | Use |
|---|---|---|
| Aluminum | Light, cheap | Low-pressure reactors |
| Stainless Steel | Strong, corrosion-resistant | PWR |
| Zirconium | Low neutron absorption | Preferred (PHWR, BWR) |
โ๏ธ Reactor Components & Control
CRITICALITY MONITOR
keff = 1.00
โ CRITICAL โ Sustained chain reaction
RADIATION SHIELDING: I = Iโยทe^(-ฮผx)
๐
Module 3 ยท Nuclear Plant: Complete Diagram & Circuit
A nuclear plant has a Primary Circuit (radioactive coolant loop through reactor & steam generator) and a Secondary Circuit (non-radioactive steam loop through turbine & condenser). Two-loop design prevents radioactive contamination of the turbine.
Primary Circuit (Radioactive)
$$\text{Reactor core} \xrightarrow{\text{Hot coolant}} \text{Steam generator} \xrightarrow{\text{Cold coolant}} \text{Pump} \rightarrow \text{Reactor}$$
Secondary Circuit (Non-radioactive)
$$\text{Steam generator} \rightarrow \text{Turbine} \rightarrow \text{Generator} \rightarrow \text{Condenser} \rightarrow \text{Pump} \rightarrow \text{Steam gen.}$$
Reactor Types
| Type | Coolant | Moderator | Fuel | Key Feature |
|---|---|---|---|---|
| PWR | Light HโO (155 bar) | Light HโO | Enriched U | Water stays liquid |
| BWR | Light HโO | Light HโO | Enriched U | Boils in reactor โ no heat exchanger |
| PHWR/CANDU | DโO | DโO | Natural U | India's main type |
| LMFBR | Liquid Na | None | Pu-239 | Breeds more fuel |
Nuclear Plant Efficiency
$$\eta_{nuclear} \approx 33\text{โ}35\% \quad (\text{lower than thermal due to lower steam conditions})$$
$$\text{But fuel cost is much lower โ economical at high load factors}$$
Nuclear Power Plant
Animated Process Flow Diagram
Hot Primary Coolant
Cool Water / Feedwater
Steam
Electricity
Nuclear Core / Neutrons
Cherenkov Radiation
Warm Condenser Water
>>>>>>> 03e68ba807ce888c12bd6ffa627b31700e71cb23
REACTOR TYPE SELECTOR
PWR (Pressurised Water Reactor): Coolant is light water under high pressure (~155 bar) โ stays liquid at ~320ยฐC. Two-loop design. Most common reactor type worldwide. Uses enriched uranium fuel.
REACTOR HEAT OUTPUT: Q = แนยทCpยทฮT
โ๏ธ
Module 3 ยท Nuclear vs Thermal Comparison
Nuclear and thermal power plants differ fundamentally in fuel, cost structure, environmental impact, and operational characteristics. Nuclear excels at base load with near-zero emissions but faces challenges in waste disposal and high capital cost.
Comparison Table
| Parameter | Nuclear | Thermal |
|---|---|---|
| Fuel | U-235, Pu-239 (tiny) | Coal, oil, gas (bulk) |
| Energy/atom | 200 MeV (fission) | ~4 eV (combustion) |
| Fuel cost | Very low | High |
| Capital cost | Very high | Moderate |
| COโ Pollution | None | High (COโ, SOโ, ash) |
| Radiation risk | Yes (if containment fails) | None |
| Load type | Base load (constant) | Base + Peak load |
| Efficiency | 33โ35% | 35โ42% |
| Waste | Radioactive (critical) | Ash (simpler) |
| India capacity | 6,780 MW (1.8%) | 2,31,421 MW (61.1%) |
Fission vs Fusion
$$\text{Fission: } ^{235}U \rightarrow \text{splits (current technology)}$$
$$\text{Fusion: } ^2H + ^3H \rightarrow ^4He + n \quad \text{(future โ ITER)}$$
$$Q_{fusion} > Q_{fission} \;\text{per kg of fuel}$$
โ๏ธ Nuclear vs Thermal Comparison
SIDE-BY-SIDE COMPARISON
FUEL COST
CAPITAL COST
COโ EMISSIONS
EFFICIENCY
INDIA SHARE
NUCLEAR vs COAL FUEL REQUIREMENT
๐
Module 3 ยท Module 3 Complete Reference
Comprehensive reference combining all Module 3 formulas โ coal classification, nuclear fission, reactor components, shielding, and plant comparison โ with interactive quiz and master calculator.
Coal Quick Reference
$$\text{Peat: } 3{,}000 \;|\; \text{Lignite: } 13{,}800\text{โ}17{,}600 \;|\; \text{Sub-bit: } 18{,}000\text{โ}23{,}000\;\text{kJ/kg}$$
$$\text{Bituminous: } 23{,}000\text{โ}34{,}000 \;|\; \text{Semi-bit: } 27{,}000\text{โ}35{,}000 \;|\; \text{Semi-anth: } 33{,}500\text{โ}34{,}750\;\text{kJ/kg}$$
Nuclear Key Formulas
$$E = mc^2 \quad;\quad {}^{235}_{92}\text{U} + n \rightarrow \text{products} + 200\;\text{MeV}$$
$$I = I_0 e^{-\mu x} \quad;\quad k_{eff} = 1 \;\text{(criticality)}$$
$$Q_{reactor} = \dot{m}_c c_p \Delta T$$
Moderator Ranking
$$D_2O\;\text{(best)} > \text{Graphite} > \text{Beryllium} > H_2O$$
Control Rod Materials
$$\text{Boron (B)},\;\text{Cadmium (Cd)},\;\text{Hafnium (Hf)}$$
๐ Quiz & Reference
QUICK QUIZ โ TEST YOUR KNOWLEDGE
Q1: CV = 28,000 kJ/kg โ which coal grade?
INDIA NUCLEAR TIMELINE
1969
Tarapur โ India's first nuclear plant (BWR)
1972
Rawatbhata PHWR (CANDU design)
2014
Kudankulam Unit 1 (VVER-1000, Russian)
Now
6,780 MW installed (1.8% of total)
2032
Target: 63,000 MW
Progress: 6,780 / 63,000 MW (10.8%)
Module 3 Part 2 โ Nuclear Reactors: Types, Fuels, Site & Performance
โข๏ธ
Module 3 ยท Reactor Components: Control Rods, Coolant, Reflector, Shielding
The reactor core contains fuel rods, control rods, moderator, coolant, reflector, and biological shielding. Together they sustain, control, and safely contain the nuclear chain reaction while extracting thermal energy for power generation.
4. Control Rods
$$\text{Purpose: Control the rate of fission of } ^{235}U$$
$$\text{Material: Boron (B), Cadmium (Cd), Hafnium (Hf)}$$
$$\text{Chain reaction controlled by: Removing fuel rods OR introducing neutron-absorbing material}$$
5. Coolant
$$\text{Medium through which heat generated in reactor is transferred to heat exchanger}$$
$$\text{Sometimes takes up heat} \rightarrow \text{converts to steam} \rightarrow \text{drives turbine (BWR type)}$$
$$\text{Gases: Air, He, H}_2\text{, CO}_2 \quad|\quad \text{Liquids: } H_2O,\;D_2O \quad|\quad \text{Metals: Na, Li}$$
6. Reflector
$$\text{Placed around core} \rightarrow \text{prevents leakage of neutrons from core}$$
$$\text{Materials: Graphite, Beryllium, Heavy water } (D_2O)$$
7. Thermal Shielding
$$\text{Protects against deadly } \alpha,\;\beta,\;\gamma \text{ radiations}$$
$$\boxed{I = I_0\,e^{-\mu x}} \quad \text{(radiation attenuation)}$$
$$\text{Shield material: Thick concrete, Lead}$$
Multiplication Factor (k)
$$\boxed{k = \frac{\text{Neutrons produced in one generation}}{\text{Neutrons produced in preceding generation}}}$$
$$k < 1:\;\text{Sub-critical (STOPS)} \quad k = 1:\;\text{Critical (STEADY)} \quad k > 1:\;\text{Super-critical (GROWS)}$$
Control Rod Action on k
$$\text{Insert rods deeper} \rightarrow \text{more neutrons absorbed} \rightarrow k \downarrow$$
$$\text{Withdraw rods} \rightarrow \text{fewer absorbed} \rightarrow k \uparrow$$
$$\text{Adjust for } k = 1 \rightarrow \text{steady power output}$$
Moderator Role
$$\text{Slow neutrons} \Rightarrow \text{slower speed} \Rightarrow \text{more likely to produce fission}$$
$$\text{Examples: Graphite, Heavy water } (D_2O)\text{, Beryllium}$$
โข๏ธ Reactor Components & k-Factor
Fuel Rods
U-235 / UOโ pellets in zircaloy cladding
Control Rods
B, Cd, Hf โ absorb neutrons
Moderator
Graphite, DโO โ slow neutrons
Coolant
HโO, DโO, COโ, Na โ removes heat
Reflector
Graphite, Be โ prevents neutron leakage
Shield
Concrete, Lead โ stops radiation
RADIATION PENETRATION DEPTH
ฮฑPaper / skin (cm)
ฮฒAluminium (mm-cm)
ฮณLead / thick concrete (m)
MULTIPLICATION FACTOR CALCULATOR
โ๏ธ
Module 3 ยท Types of Nuclear Reactors
Six major reactor types form the backbone of nuclear power worldwide. They differ in fuel, coolant, moderator, and thermodynamic efficiency โ from the common BWR/PWR to the advanced Fast Breeder Reactor.
1. Boiling Water Reactor (BWR)
$$\text{Fuel: Enriched UO}_2 \quad \text{Coolant/Moderator: Light water}$$
$$\text{Water boils directly in reactor} \rightarrow \text{steam drives turbine (single loop)}$$
2. Pressurised Water Reactor (PWR)
$$\text{Fuel: Enriched UO}_2\;\text{(clad in zircaloy)} \quad \text{Thermal reactor}$$
$$T_{primary} \approx 320ยฐC,\quad P \approx 155\;\text{bar (water stays liquid)}$$
3. Advanced Gas Cooled Reactor (AGCR)
$$\text{Fuel: U-235} \quad \text{Coolant: CO}_2 \quad \text{Moderator: Graphite}$$
4. CANDU (Canadian Deuterium Uranium)
$$\text{Fuel: Natural Uranium} \quad \text{Moderator: } D_2O \quad \text{Coolant: } D_2O$$
$$\text{Advantage: No enrichment needed โ India's PHWR based on CANDU design}$$
5. Liquid Metal Cooled Reactor (LMCR)
$$\text{Fuel: Uranium} \quad \text{Coolant: Liquid Na} \quad \text{Na} \rightarrow \text{Heat} \rightarrow \text{Steam}$$
6. Fast Breeder Reactor (FBR)
$$\text{Fuel: Pu-239 / Th-232} \quad \text{Coolant: Liquid Na} \quad \text{Moderator: NONE}$$
$${}^{238}_{92}\text{U} + {}^{1}_{0}n \rightarrow {}^{239}_{92}\text{U} \xrightarrow{\beta^-} {}^{239}_{93}\text{Np} \xrightarrow{\beta^-} {}^{239}_{94}\text{Pu}$$
$$\eta_{FBR}(\text{Na}) \approx 42\% \quad \eta_{other} \approx 28\% \quad \text{FBR most efficient!}$$
Reactor Comparison Table
$$\text{BWR: Enriched UO}_2\;|\;\text{Light water}\;|\;\text{Light water}\;|\;33\%$$
$$\text{PWR: Enriched UO}_2\;|\;\text{Light water (pressure)}\;|\;\text{Light water}\;|\;33\%$$
$$\text{AGCR: U-235}\;|\;\text{CO}_2\;|\;\text{Graphite}\;|\;40\%$$
$$\text{CANDU: Natural U}\;|\;D_2O\;|\;D_2O\;|\;30\%$$
$$\text{LMCR: Uranium}\;|\;\text{Liquid Na}\;|\;\text{โ}\;|\;35\%$$
$$\text{FBR: Pu-239/Th-232}\;|\;\text{Liquid Na}\;|\;\text{None}\;|\;42\%$$
โ๏ธ 6 Reactor Types โ Interactive
BWR โ Boiling Water Reactor
FuelEnriched UOโ
CoolantLight water (boils in core)
ModeratorLight water
Efficiency~33%
NoteTarapur (India) โ first nuclear plant, BWR type
PWR โ Pressurised Water Reactor
FuelEnriched UOโ (zircaloy clad)
CoolantLight water under 155 bar
ModeratorLight water
Efficiency~33%
NoteKudankulam (India) โ PWR type
AGCR โ Advanced Gas Cooled Reactor
FuelU-235
CoolantCOโ gas
ModeratorGraphite
Efficiency~40%
NoteDeveloped in UK โ higher operating temperature than PWR
CANDU / PHWR โ Heavy Water Reactor
FuelNatural Uranium (no enrichment!)
CoolantDโO (heavy water)
ModeratorDโO (heavy water)
Efficiency~30%
IndiaRawatbhata, Kaiga, Kakrapar โ India's primary reactor type
LMCR โ Liquid Metal Cooled Reactor
FuelUranium
CoolantLiquid Sodium (Na)
Moderatorโ
Efficiency~35%
NoteIntermediate heat exchanger: Na โ Heat โ Steam
FBR โ Fast Breeder Reactor โญ
Breeds more fissile material (Pu-239) than it consumes! Breeding ratio > 1
FuelPu-239 / Th-232
CoolantLiquid Sodium (Na)
ModeratorNONE (fast neutrons)
Efficiency~42% (HIGHEST!)
IndiaPFBR Kalpakkam โ India's 3-stage nuclear programme
Breeding: ยฒยณโธU + n โ ยฒยณโนU โ(ฮฒโป)โ ยฒยณโนNp โ(ฮฒโป)โ ยฒยณโนPu
EFFICIENCY COMPARISON
โญ FBR with liquid Na: Highest efficiency at 42%
โ๏ธ
Module 3 ยท Nuclear Fuels & Plutonium Formation
Nuclear fuels include natural uranium (U-235, U-238), enriched uranium, and bred fuels (Pu-239 from U-238, U-233 from Th-232). The conversion of fertile U-238 to fissile Pu-239 via neutron capture and beta decay is key to the Fast Breeder Reactor programme.
Fission Products
$${}^{235}_{92}\text{U} + {}^{1}_{0}n \rightarrow {}^{141}_{56}\text{Ba} + {}^{92}_{36}\text{Kr} + 3\;{}^{1}_{0}n + Q$$
$$\text{OR: } \rightarrow {}^{140}_{55}\text{Cs} + {}^{94}_{37}\text{Rb} + 2\;{}^{1}_{0}n + 200\;\text{MeV}$$
Plutonium-239 Formation (3-Step)
$$\text{Step 1 (immediately): } {}^{238}_{92}\text{U} + {}^{1}_{0}n \rightarrow {}^{239}_{92}\text{U}$$
$$\text{Step 2 (23 min): } {}^{239}_{92}\text{U} \xrightarrow{\beta^-} {}^{239}_{93}\text{Np} + e^- + \bar{\nu}$$
$$\text{Step 3 (2.3 days): } {}^{239}_{93}\text{Np} \xrightarrow{\beta^-} {}^{239}_{94}\text{Pu} + e^- + \bar{\nu}$$
$$\boxed{{}^{238}_{92}\text{U} \xrightarrow{+n} {}^{239}_{92}\text{U} \xrightarrow{23\;\text{min}} {}^{239}_{93}\text{Np} \xrightarrow{2.3\;\text{days}} {}^{239}_{94}\text{Pu}}$$
Why Pu-239 Matters
$$\text{Pu-239 is fissile (like U-235) โ FBR breeds it from abundant U-238 (99.3\% of natural U)}$$
Thorium Fuel Cycle (India)
$${}^{232}_{90}\text{Th} + n \rightarrow {}^{233}_{90}\text{Th} \xrightarrow{\beta^-} {}^{233}_{91}\text{Pa} \xrightarrow{\beta^-} {}^{233}_{92}\text{U}$$
$$\text{India has } \approx 25\% \text{ of world's thorium reserves (Kerala coast)}$$
Energy per Fission
$$Q = 200\;\text{MeV} = 3.2 \times 10^{-11}\;\text{J per fission}$$
$$\text{Per kg U-235: } E = \frac{6.023\times10^{23}}{235} \times 3.2\times10^{-11} \approx 8.2\times10^{13}\;\text{J} = 8.2\times10^7\;\text{MJ/kg}$$
โ๏ธ Plutonium Formation & Decay Chain
Pu-239 FORMATION CHAIN
U-238
Fertile
+n โinstant
U-239
Unstable
ฮฒโป โ23 min
Np-239
Intermediate
ฮฒโป โ2.3 days
Pu-239
Fissile!
FISSION ENERGY CALCULATOR
๐ฎ๐ณ
INDIA'S THORIUM ADVANTAGE
ยฒยณยฒTh โ ยฒยณยณU fuel cycle | ~25% of world's thorium reserves
Stage 3 of India's 3-stage nuclear programme
๐
Module 3 ยท Selection of Plant Site
Nuclear plant site selection involves safety exclusion zones, water availability, accessibility, and waste disposal space. Nuclear plants offer low operating cost but high initial investment, heavy cooling requirements, and radioactive waste challenges.
Site Selection Criteria
$$\text{1. Availability of water supply} \quad \text{2. Accessibility / Type of land}$$
$$\text{3. Distance from populated areas (safety exclusion zone)}$$
$$\text{4. Transportation facilities} \quad \text{5. Nearness to load center}$$
$$\text{6. Availability of space for disposal of waste}$$
Safety Zones
$$R_{exclusion} \geq 1.6\;\text{km (typical minimum)}$$
$$\text{Low population zone: 5โ10 km radius}$$
$$Q_{cooling} \approx 30\text{โ}50\;\text{m}^3/\text{s for a 1000 MW plant}$$
Advantages
$$\text{1. Can be constructed near load centers (negligible transport cost)}$$
$$\text{2. Most economical for large MVA rating}$$
$$\text{3. Operating cost is very low}$$
Disadvantages
$$\text{1. Initial cost very high} \quad \text{2. Radioactive waste โ pollution}$$
$$\text{3. Not suitable for varying loads (base load only)}$$
$$\text{4. Fuel expensive, difficult to recover} \quad \text{5. Very heavy cooling water requirement}$$
Efficiency & Radioactive Decay
$$\boxed{\eta_{nuclear} = 30\text{โ}40\%} \quad \eta_{overall} = \eta_{reactor} \times \eta_{turbine} \times \eta_{generator}$$
$$\text{FBR with Na: } \eta \approx 42\% \quad \text{Other coolant: } \eta \approx 28\%$$
$$N(t) = N_0 \cdot 2^{-t/t_{1/2}} \quad \text{(radioactive decay of waste)}$$
๐ Site Selection & Safety Zones
SAFETY EXCLUSION ZONES
10 km โ Planning zone
5 km โ Low pop.
1.6 km
ADVANTAGES vs DISADVANTAGES
โ ADVANTAGES
Near load centers โ negligible transport cost
Most economical for large MVA rating
Very low operating cost
โ DISADVANTAGES
Very high initial cost
Radioactive waste โ pollution
Not suitable for varying loads
Fuel expensive & hard to recover
Heavy cooling water requirement
RADIOACTIVE DECAY CALCULATOR
OVERALL EFFICIENCY
๐
Module 3 ยท Complete Nuclear Reference
Master reference combining all nuclear power formulas โ reactor types, multiplication factor, radiation shielding, fission energy, Pu-239 breeding, radioactive decay, and efficiency โ with interactive quiz and flip-card reactor reference.
All Key Nuclear Formulas
$$E = mc^2 \quad;\quad k = \frac{n_{gen+1}}{n_{gen}}\;\;(k=1:\text{critical})$$
$$Q_{fission} = 200\;\text{MeV/fission} \quad;\quad I = I_0 e^{-\mu x}$$
$$N(t) = N_0 \cdot 2^{-t/t_{1/2}} \quad;\quad \eta_{FBR} = 42\%,\;\eta_{nuclear} = 30\text{โ}40\%$$
Pu-239 Formation Chain
$$^{238}U \xrightarrow{+n} ^{239}U \xrightarrow{23\;\text{min}} ^{239}Np \xrightarrow{2.3\;\text{days}} ^{239}Pu$$
6 Reactor Types Quick Reference
$$\text{BWR: Enriched U | Water | Water | 33\%}$$
$$\text{PWR: Enriched U | Water (pressure) | Water | 33\%}$$
$$\text{AGCR: U-235 | CO}_2\text{ | Graphite | 40\%}$$
$$\text{CANDU: Natural U | }D_2O\text{ | }D_2O\text{ | 30\%}$$
$$\text{LMCR: Uranium | Liquid Na | โ | 35\%}$$
$$\text{FBR: Pu-239 | Liquid Na | None | 42\%}$$
Moderator Ranking & Control Rod Materials
$$D_2O > \text{Graphite} > \text{Beryllium} > H_2O$$
$$\text{Control rods: Boron (B), Cadmium (Cd), Hafnium (Hf)}$$
๐ Master Quiz & Flip Cards
NUCLEAR REACTOR QUIZ
Q1: Which reactor type uses natural uranium (no enrichment)?
k-FACTOR TRAINER
Scenario: Control rods are inserted deeper. What happens to k?
REACTOR FLIP CARDS โ Click to reveal
BWR
Click to flip
Enriched UOโ
Water / Water
ฮท โ 33%
Tarapur ๐ฎ๐ณ
Water / Water
ฮท โ 33%
Tarapur ๐ฎ๐ณ
PWR
Click to flip
Enriched UOโ
Water (155 bar) / Water
ฮท โ 33%
Kudankulam ๐ฎ๐ณ
Water (155 bar) / Water
ฮท โ 33%
Kudankulam ๐ฎ๐ณ
AGCR
Click to flip
U-235
COโ / Graphite
ฮท โ 40%
UK design
COโ / Graphite
ฮท โ 40%
UK design
CANDU
Click to flip
Natural U (no enrich!)
DโO / DโO
ฮท โ 30%
Rawatbhata ๐ฎ๐ณ
DโO / DโO
ฮท โ 30%
Rawatbhata ๐ฎ๐ณ
LMCR
Click to flip
Uranium
Liquid Na / โ
ฮท โ 35%
Na intermediate HX
Liquid Na / โ
ฮท โ 35%
Na intermediate HX
FBR โญ
Click to flip
Pu-239 / Th-232
Liquid Na / None
ฮท โ 42% (BEST!)
Kalpakkam ๐ฎ๐ณ
Liquid Na / None
ฮท โ 42% (BEST!)
Kalpakkam ๐ฎ๐ณ
INDIA NUCLEAR TIMELINE
1969
Tarapur BWR โ first nuclear plant
1972
Rawatbhata CANDU/PHWR
2013
Kudankulam PWR
2024
PFBR Kalpakkam (FBR)
2032
Target: 63,000 MW nuclear capacity
Module 4 โ Diesel, Gas Turbine & Non-Conventional Energy