Nuclear Fission Reactors

Nuclear Fission Reactors

This article deals with ‘Nuclear Fission Reactors .’ This is part of our series on ‘Science and Technology’ which is important pillar of GS-3 syllabus . For more articles , you can click here.


Nuclear Fission

  • In 1939, Otto Hahn and Strassman discovered Nuclear Fission when they found that a slow-moving neutron collides with a uranium nucleus; it breaks into two smaller nuclei of comparable masses with the release of energy. 
  • In simple words, Nuclear Fission means breaking up the heavier nucleus into two smaller nuclei and releasing an enormous amount of energy.
Nuclear Fission Reaction
  • Reactant total mass is more than product total mass & EXCESS mass is converted to energy (using Einstein’s Mass – Energy Relation (E = mc^2)). The energy released from 1 nucleus of Uranium (235) is nearly 93 Mega Electron Volt. When one Uranium nucleus undergoes fission, the energy released might be small. But from each fission reaction, three neutrons are released. These three neutrons can cause further fission in three other Uranium nuclei. This process is called a chain reaction.
  • The energy produced in the nuclear reaction can be used to convert water into steam, which can be converted into electricity using Steam Turbine and Generator.

Types of Reactors

A simple Nuclear Reactor from which electricity can be generated is of following type

Types of Reactors
Fuel U-235, U-233, Pu – 239 or Th -232 is used as fuel in the Nuclear Reactor  
Moderator It reduces the speed of neutrons so that nuclear reactions can take place. 
– Graphite or Heavy Water (D2O) is used as Moderator.  
Coolant The coolant absorbs the energy/heat released from the reaction and transfers it into turbines.
Heavy Water or Water can be used as coolant (depending on the type of Reactor)  
Control Rods To control the speed of the Nuclear Reactor.
Boron or Cadmium is used as Control Rod.  
Concrete Shield Concrete wall with 2-5 m thickness to stop radiation from spreading.

Reactors used in India

1. Pressurized Heavy Water Reactor (PHWR)

Most of the Nuclear Reactors found in India are PHWRs.


Information at Glance

Fuel Natural Uranium (without enrichment) (It is easier to make and less expensive to use, as Uranium enrichment is a complex process)
Coolant Heavy Water/Deuterium Oxide
By Products Plutonium  (more amount )
Moderator Heavy Water/Deuterium Oxide (Moderator and coolant are same) => Neutrons collide with Heavy Water molecules and slow them.  
Why Pressurized If water is heated, it expands & becomes less dense. As a result probability of collision between neutrons and water molecules to reduce the speed of neutrons decreases. It is crucial to decrease the speed of neutrons to ensure fission.
Cost Less Expensive
Pressurized Heavy Water Reactor (PHWR)

Details of PHWRs

The primary reaction which leads to the generation of energy while using Uranium as fuel is

Nuclear Fission Reaction
  • The most crucial point in Uranium Fission Reaction is the release of an extra 2.5 (average) Neutrons, which leads to the possibility of a chain reaction. If controlled, it can be used to produce energy called Nuclear Energy. At the same time, if it remains uncontrolled, it can result in an Atomic Bomb.
  • But the biggest hurdle, in this case, is the fact that neutrons liberated in the nuclear reaction are fast-moving & will not cause fission (instead, they will escape without causing any collision). To ensure a Fission reaction, these neutrons must be slowed. For this purpose, Moderators are used, which in this case are D2O (Heavy Water) & Graphite.
  • The reaction rate can be controlled by Control Rods, which are made up of neutron-absorbing material like Cadmium
  • The energy released in fission is continuously removed by a suitable Coolant which transfers heat to a working fluid which in turn may produce steam to drive the turbine & generate electricity. 
  • Pressuriser is used because when heavy water is heated, it expands & becomes less dense. As a result probability of collision between neutrons and heavy water molecules to reduce the speed of neutrons decreases. It is crucial to decrease the speed of neutrons to ensure fission. The Pressuriser ensures the suitable density of the heavy water.

2. Boiling Water Reactor (BWR)

  • It is the oldest type of Nuclear Reactor.
  • Fuel Used: Enriched Uranium
  • Working: Energy released during the fission reaction directly heats the (light) water. The same water is used to turn the turbine and then recycled back, to be used again in the cycle.
  • Moderator: No Moderator is used. The probability of neutron colliding with U-235 is achieved by using Enriched Uranium.
Boiling Water Reactor (BWR)
  • BWRs are the second most widely used reactors in the world. But in India, we don’t use them on a large scale. Tarapur Atomic Power Station was constructed initially with two boiling water reactors (BWR) under the 1963 Agreement between India, USA & International Atomic Energy Agency (IAEA).

Issue with BWR

  • The use of enriched Uranium increases cost and complexities.
  • Light water is directly heated by radioactive material. Hence, nuclear radiation fallout in case of an accident is maximum in such reactors. For example, Japan’s Fukushima Nuclear reactor, which caused great damage after a nuclear accident, was BWR. 

3. Fast Breeder Reactor

  • Fast Breeder Reactor produces the same kind of fissile material as it burns.
  • While using Pu239 as fuel, it can produce more Pu239 than it consumes by converting non-fissionable U-238 present in the natural Uranium.
  • With fast neutrons, the chances of absorption by U-238 increase. Additionally, Pu-239 produces extra neutrons in the case of a collision with fast-moving neutrons only. Hence, these reactors don’t use moderators to slow down the neutrons.
  • Liquid sodium or steam coolants are used in FBRs. 
  • India’s BHAVINI nuclear reactor is Prototype Fast Breeder Reactor.
Fast Breeder Reactor

Prelims Related: List of BARC Atomic Reactors

Apsara First Atomic Reactor in 1957  
Cirus Indo-Canadian Reactor
Operational Period: 1960-2010
Zerlina Operationalized in 1961
To study Uranium Heavy Water Reactors
Dhruva Operationalized in 1984
Completely indigenous reactor
Purnima -1  
Kamini – India’s first Fast Breeder Reactor.
Installed in Kalpakkam
India is 7th country in world to have FBR

Indian Three Stage Nuclear Program

Indian Three Stage Nuclear Program

This article deals with ‘Indian Three Stage Nuclear Program.’ This is part of our series on ‘Science and Technology’ which is an important pillar of the GS-3 syllabus. For more articles, you can click here


Introduction

Indian Three Stage Nuclear Program
  • Homi Bhabha formulated India’s 3-Stage Nuclear Program. 
  • The reason for the formulation of this program was that India has the largest source of Thorium and modest deposits of Uranium. Considering this fact, Dr Homi Bhabha envisioned 3-Stage Nuclear Program in 1954. It aimed to secure India’s long-term energy independence by using Uranium and Thorium reserves found in the Monazite sands of coastal India. 
  • Note: India has only 1-2% of the global Uranium but about 30% of the world’s Thorium.

Stage 1

The first stage involves the utilization of Pressurized Heavy Water Reactors (PHWR) fuelled by natural Uranium. In this stage, natural Uranium is used as a fuel, and heavy water (deuterium oxide) is used as a moderator and coolant. India has built several PHWRs, which generate electricity and produce plutonium-239 as a by-product (to be used as fuel for the next stage.)


Overview

Reactor

  • Pressurized Heavy Water Reactor (PHWR)

Fuel used

  • Natural Uranium (Note: It is not enriched. Just Natural Uranium is used.)

Moderator and coolant

  • Heavy Water (D2O/Deuterium Oxide)

Reaction

Main Reaction (Energy)

Stage 1 of Nuclear Energy: Reaction 1

Other  (to get Pu -239)

Stage 1 of Nuclear Energy: Reaction 2

Process explained

  • Natural Uranium contains both U-238 and U-235 in the following proportions.
Natural Uranium - composition
  • In Nuclear Reactor, when a slow-moving Neutron is bombarded on the Uranium fuel, it collides with and splits U-235 nuclei, thus releasing a large amount of energy and 3 neutrons. The production of 3 neutrons helps in making it a chain reaction. 
  • Some of the neutrons will get absorbed into U-238, thus converting it into Pu-238 (Plutonium-238, which is fissile). Pu-238, thus generated, acts as fuel in the second stage.

Pressurized Heavy Water Reactor

Pressurized Heavy Water Reactor

Why is Heavy Water is used as Moderator?

  • A moderator in the form of Heavy Water is used to decrease the speed of neutrons produced in the nuclear reaction because it increases the probability of fission with Uranium-235, even though its proportion is just 0.7% in natural Uranium. 
  • Heavy water slows down neutrons by their repeated collisions with neutrons.

Control Rods

  • To reduce the power level or to shut down the reactor, the reaction rate is lowered by decreasing the number of available neutrons. It is achieved with the help of control rods like Boron or Cadmium Rods, which can absorb the neutrons.

The operator of PHWR or First Stage of the Indian Nuclear Program 

  • PHWR is operated by NPCIL or Nuclear Power Corporation of India Limited. 
  • Almost the entire base of Indian nuclear power is composed of stage 1 PHWRS except for the two Boiling Water Reactors (BWRs) at Tarapore.

Stage 2

Fast Breeder Reactor

Stage 2 of Indian Three Stage Nuclear Program

Overview

The second stage focuses on utilizing Fast Breeder Reactors. FBRs use Plutonium-239 obtained from the spent fuel of PHWRs as the fuel and liquid sodium as the coolant. These reactors can generate more fissile material (Plutonium-239) than they consume. Thorium would be added to the fuel cycle once sufficient stock had been amassed to transform it into uranium 233 for the third stage.

Reactor

  • FBR (Fast Breeder Reactor )

Fuel used

Mixed oxide (MOX) fuel (received from first stage) consisting of

Pu-239 Undergo fission to produce more energy
U-238 Undergo change to additional Pu239

Moderator 

  • FBR doesn’t use a Moderator, as only fast-moving neutrons produce extra neutrons on collision with Pu-239.

Coolant

  • Liquid Sodium 

Crucialties of Stage 2

Further, 2nd stage is crucial for 3rd stage as it converts Thorium-232 (which occurs naturally) into Uranium–233 by transmutation

  • Once there is a good reserve of Pu-239, Th-232 is introduced at the periphery of the core (blanket material).
  • The collision with neutrons will convert Th-232 to U-233 (which is fissile).

Stage 3

Thorium Based Reactors

Stage 3 of Indian 3 Stage Nuclear Programme

The program’s third and final stage involves deploying Advanced Heavy Water Reactors. AHWRs are designed to use a mix of Thorium-232 and Uranium-233 (obtained as a by-product from 2nd stage) as fuel. Additionally, The Th-232 will be placed at the periphery of the Core fuel, resulting in additional U-233 fuel.


It’s important to note that while India has made significant progress in the first two stages, the third stage of the program is still in the developmental phase, and commercial deployment of AHWRs is yet to take place.


Thorium as Nuclear Fuel

India & Thorium

  • India has the largest reserve of Thorium in the world and consists of 30% of the world’s Uranium reserves
  • Main Indian reserves include 
    • Monazite beach sand in Kerala 
    • Found in Andhra (largest producer), Tamil Nadu, Odisha, Kerala and West Bengal

Advantages

  • Thorium is more abundant (4 times more) than Uranium in the Earth’s crust. 
  • Thorium consists of a single isotope, Th-232, unlike Uranium. Hence there is no need for the isotope separation. 
  • Thorium-based fuels have favourable physical and Chemical properties that improve the reactor’s performance. These include
    • Higher melting point 
    • Higher thermal conductivity 
    • Low coefficient of thermal expansion 
    • Greater chemical stability 
    • Doesn’t further oxidise 
  • The long-term radiological hazard of Uranium based nuclear fuel, dominated by Plutonium and other Actinides is not there in Thorium based fuel. 

Disadvantages

  • No fissile isotopes in natural Thorium
  • The high sintering temperature required to make Thorium Oxide 
  • Long interval over which Thorium 232 breeds to Uranium 233