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IGCAR : Annual Report - Indira Gandhi Centre for Atomic Research

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IGC<br />

<strong>Annual</strong> <strong>Report</strong> 2007<br />

The construction of PFBR has<br />

progressed very well (Fig.1-3).<br />

The manufacturing of safety<br />

vessel with thermal insulation,<br />

large diameter main sodium<br />

and argon tanks, and thermal<br />

baffles has been completed.<br />

Manufacturing of long delivery<br />

mechanical components of<br />

Nuclear Steam Supply System<br />

(NSSS), viz grid plate,<br />

shutdown mechanisms, core<br />

support structure, top shields,<br />

IHX, sodium pumps, steam<br />

generators, inclined fuel<br />

Fig.1 Overall view of the reactor site<br />

transfer machine and decay<br />

heat removal heat exchangers<br />

are in different stages of<br />

progress in Indian industries.<br />

Manufacturing of main vessel<br />

and inner vessel is in advanced<br />

stage at site assembly shop.<br />

Construction of 8 numbers of<br />

Nuclear Island Connected<br />

Buildings, diesel generator<br />

buildings, service building,<br />

service water pump house and<br />

ventilation stack is in progress<br />

at various elevations. The<br />

Fig.2 Reactor vessel<br />

Fig.3 Safety vessel<br />

contracts <strong>for</strong> construction of<br />

turbine building, sea-water<br />

intake structure and sea-water<br />

outfall channel have been<br />

awarded.<br />

Purchase orders have been<br />

placed <strong>for</strong> main plant<br />

turbo generator package,<br />

instrumentation and control<br />

package, 6.6 kV switchgear,<br />

diesel generators, switchyard<br />

and main cranes. Overall, the<br />

project is on schedule and the<br />

reactor is expected to be<br />

commissioned by September<br />

2010.<br />

II.2. Design and Development of<br />

Thermal Insulation <strong>for</strong> Safety Vessel<br />

In PFBR, which is a 500 MWe<br />

sodium cooled pool type<br />

reactor, all reactor internals<br />

including core and primary<br />

coolant (sodium) are contained<br />

in a single vessel called main<br />

vessel surrounded by safety<br />

vessel, which serves the<br />

purpose of containing sodium<br />

and ensuring minimum sodium<br />

level to facilitate core cooling<br />

in the unlikely event of leak in<br />

main vessel. The load from<br />

these vessels is transferred to<br />

concrete structure known as<br />

reactor vault. To limit the heat<br />

flux to reactor vault concrete<br />

and thereby ensuring the<br />

integrity of the same, stainless<br />

steel plate type thermal<br />

insulation which can withstand<br />

high gamma radiation is<br />

provided on outer surface of<br />

the safety vessel.<br />

Design<br />

Thermal insulation on safety<br />

12 PROTOTYPE FAST BREEDER REACTOR

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