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Nuclear Energy

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Coolant: A liquid or gas circulating through the core so as to transfer the heat from it. In light water<br />

reactors, the moderator which is water also serves as the primary coolant. Except in Boiling Water<br />

Reactors (BWRs), this primary coolant passes through another heat exchanger, to convert another<br />

loop of water into steam. This steam drives the turbine. The advantage of this design is that the<br />

radioactive water/steam (that is, the primary coolant) does not come into contact with the turbine.<br />

Pressure vessel: Usually a robust steel vessel containing the reactor core and moderator/coolant.<br />

Steam generator (not in BWR) or Secondary heat exchanger: Here, the primary coolant bringing<br />

heat from the reactor is used to convert another loop of water into steam to drive the turbine.<br />

Containment: The structure around the reactor core which is designed to protect it from outside<br />

intrusion and to protect those outside from the effects of radiation in case of any malfunction inside.<br />

It is typically a metre-thick concrete and steel structure.<br />

Refuelling the reactors: In most reactors, the refuelling is done at intervals of 1-2 years, when a<br />

quarter to one-third of the fuel assemblies are replaced with fresh ones. For this, the reactor needs to<br />

be shut down. But in the CANDU type reactors, which have pressure tubes (rather than a pressure<br />

vessel enclosing the reactor core) and can be refuelled under load by disconnecting individual<br />

pressure tubes, the reactor need not be shut down.<br />

Types of <strong>Nuclear</strong> Power Reactors<br />

At a basic level, reactors may be classified into two classes: Light Water Reactors (LWRs)<br />

and Heavy Water Reactors (HWRs). LWRs are largely of two types, Pressurised Water Reactors<br />

(PWRs) and Boiling Water Reactors (BWRs); each come in multiple variations.. Heavy Water<br />

Reactors can be of different types, one of the most well known being the CANDU (acronym for<br />

“CANada Deuterium Uranium”) reactors developed by Canada which are a type of Pressurised<br />

Heavy Water Reactors (PHWRs).<br />

LWRs are the most widespread type of reactors in operation today. Of the 437 reactors in<br />

operation at the end of 2009, 357 were LWRs, of which 265 were PWRs and 92 BWRs. Apart from<br />

these, the other reactor types in operation were: 45 pressurized heavy-water reactors (PHWRs), 18<br />

gas-cooled, graphite-moderated reactors, (GCRs), 15 light-water-cooled, graphite-moderated<br />

reactors (LWGR), and 2 fast breeder reactors (FBRs). liii<br />

Below, we discuss the most well-known type of nuclear power reactor – the PWR, the<br />

reactor design of most of India's reactors - the PHWR or CANDU <strong>Nuclear</strong> Power Reactor, and also<br />

the Fast Breeder Reactor, which India has been trying to build for many decades and of which there<br />

are only two reactors in operation today, a prototype unit in Japan and the BN-600 reactor Russia<br />

(which is technically not a fast breeder – See Chapter 9).<br />

(i) Pressurised Water Reactor<br />

This is the most common type, with 265 in use for power generation and several hundred<br />

more employed for naval propulsion. PWRs use ordinary water as both coolant and moderator.<br />

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