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Pressurized Heavy Water Reactor [PHWR] - Indigenous Indian Design

gslv mk3

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Pressurized Heavy Water Reactor [PHWR] - Indigenous Indian Design

http://www.aame.in/2013/09/pressurized-heavy-water-reactor-phwr.html

The Indian programme envisages building commercial scale electricity generating Reactors that operate on a broad spectrum of Nuclear cycles. These include the thorium-utilising Fast Breeder Reactors & systems for harnessing the power of Nuclear fusion, Work is also underway for developing Compact High Temperature Reactor [CHTR] that could provide electricity to regions not connected to the grid & be utilised for large-scale generation of hydrogen.

While these systems reside, somewhat, in the realms of the "exotic", NPCIL has also developed & deployed indigenous power plants utilising the more prevalent nuclear fuel cycle, with its Pressurized Heavy Water Reactor [PHWR]-series. "Burning" natural Uranium, the 1st of its Reactors became operational on the 1st of January 1991. Since then, NPCIL has been successful in scaling up the design.

Currently PHWR plant designs exist in 3 power ratings - 220, 540 & 700 MWe. While the 220 & 540-rated reactors have been in operation for many years [the 1st 540 MWe design began operation in 2005], work on setting up the larger 700 MWe plant continues at the sites of Kakrapar & Rajasthan power-plants. They are expected to start electricity generation in 2015 [Rajasthan, 2016]. Unlike the earlier 2 types, the 700 MWe-reactor will use Slightly Enriched Uranium [SEU] as fuel. In addition to the 4 reactors being set up at the 2 locations, 16 more of these advanced PHWR designs are being planned for construction at 5 locations.

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In this NPCIL presentation, the 3 designs have been compared, highlighting their key features & technologies, including safety aspects.
In keeping with best practices, critical functions of the reactor have been equipped with dual-redundant systems, for fail-safe operation. In order to realise the PHWR, it developed & demonstrated manufacturing processes & systems requiring compliance to exacting standards. These include ultra heavy forging, zero-leak high discharge canned rotor pumps for circulating the heavy water, automated on-power refuelling machine, all requiring manufacturing adhering to the highest Class-1 standards.(see pics below)
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i suppose they have started commercial use of pressurised heavy water
 
..Developing and making them operational are entirly two different ball game.
We had historically been weak on the second issue...
Construction & comissioning of a nuclear plant takes a decade, which should be brought down to max. 5 years..
Wish Jaitapur starts soon...but soon is a very broad term... :(
 
The gem -AHWR 300

nuke2rr2.jpg


@DESERT FIGHTER
...Do you know understand that India can now develop and build nuclear reactors upto 900 MW on its own??
:rolleyes::cool:
 
Nope, this has French and Russian designs written all over it.

This is yet another Indian lie. Importing foreign components and assembling it in India doesn't make this 'Indian'.

Sorry to burst your bubble but India has not designed and manufactured its own nuclear reactors with 100% indigenous components. Until that day comes, India has achieved jack all in nuclear technology.
 
Nope, this has French and Russian designs written all over it.

This is yet another Indian lie. Importing foreign components and assembling it in India doesn't make this 'Indian'.

Sorry to burst your bubble but India has not designed and manufactured its own nuclear reactors with 100% indigenous components. Until that day comes, India has achieved jack all in nuclear technology.
Dude... you have not burst any bubble.
Where did you see the French and Russian designs in all that was posted?
Regarding 100% indigenous components, it makes no sense in not using commercially available cheaper parts from sources. And please do quote from reliable sources which parts you have objections about.
 
Nope, this has French and Russian designs written all over it.

This is yet another Indian lie. Importing foreign components and assembling it in India doesn't make this 'Indian'.

Sorry to burst your bubble but India has not designed and manufactured its own nuclear reactors with 100% indigenous components. Until that day comes, India has achieved jack all in nuclear technology.

OMG Chinese troll.I see you are jealous with Indian advancements in Fast Breeder Reactors & Thorium Reactors...while you are building experimental FBRs & MSRs....:rolleyes:

So get lost !
 
Nope, this has French and Russian designs written all over it.

This is yet another Indian lie. Importing foreign components and assembling it in India doesn't make this 'Indian'.

Sorry to burst your bubble but India has not designed and manufactured its own nuclear reactors with 100% indigenous components. Until that day comes, India has achieved jack all in nuclear technology.


it is thorium fueled reactor. rusian and french are not an expert on this kind of reactors. this is fully indian design.
 
@gslv mk3

What do you need clarification on ?

I already explained a long time ago , how the " shaped trajectory system " described by DRDO on Shaurya isn't cruise missile designation nor indicates at that . It can be best classified as " quasi ballistic missile " borrowing certain characteristics from cruise missile but still being " ballistic missiles " - meaning the flight path will be not completely " ballistic " in nature but yet will not be much different from it . As for the speed creating confusion for you , let me assure that " ballistic missiles " go much much higher than Mach 6 during their flight . A good example being the CM 400 AKG itself . Hope that clears it up .
 
OMG Chinese troll.I see you are jealous with Indian advancements in Fast Breeder Reactors & Thorium Reactors...while you are building experimental FBRs & MSRs....:rolleyes:

So get lost !

India’s first 40 MWt Fast Breeder Test Reactor (FBTR) attained criticality on 18 October 1985.

The Fast Breeder Test Reactor (FBTR) is a breeder reactor located at Kalpakkam, India.[1] The Indira Gandhi Center for Atomic Research (IGCAR) and Bhabha Atomic Research Center (BARC) jointly designed, constructed, and operate the reactor.

It first reached criticality in October 1985, making India the sixth nation to have the technology to build and operate an FBTR after United States, UK, France, Japan and the former USSR

The China Experimental Fast Reactor (CEFR) is a 25 MW(e) prototype for the planned China Prototype Fast Reactor (CFRP).[83] It started generating power on 21 July 2011.[84]
 
^^^^
Plus Kaveri is all set to power Rajput Class Destroyers too...:)
 

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