IGCAR : Annual Report - Indira Gandhi Centre for Atomic Research
IGCAR : Annual Report - Indira Gandhi Centre for Atomic Research
IGCAR : Annual Report - Indira Gandhi Centre for Atomic Research
You also want an ePaper? Increase the reach of your titles
YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.
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