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Indian scientists to design thorium reactor

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Indian scientists to design thorium reactor

Sunday, July 01, 2007
17:36 IST

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Bangalore: A team of scientists at a premier Indian nuclear facility has made a theoretical design of an innovative reactor that can run on thorium - available in abundance in the country - and will eventually do away with the need for uranium.



The novel Fast Thorium Breeder Reactor (FTBR) being developed by V. Jagannathan and his team at the Bhabha Atomic Research Centre (BARC) in Mumbai has received global attention after a paper was submitted to the International Conference on Emerging Nuclear Energy Systems (ICENES) held June 9-14 in Istanbul.


Power reactors mostly use a fissile fuel called uranium-235 (U-235), whose "fission" releases energy and some "spare" neutrons that maintain the chain reaction.


But only seven out of 1,000 atoms of naturally occurring uranium are of this type. The rest are "fertile", meaning they cannot fission but can be converted into fissionable plutonium by neutrons released by U-235.


Thorium, which occurs naturally, is another "fertile" element that can be turned by neutrons into U-233, another uranium isotope. U-233 is the only other known fissionable material. It is also called the "third fuel".


Thorium is three times more abundant in the earth's crust than uranium but was never inducted into reactors because - unlike uranium - it has no fissionable atoms to start the chain reaction.

But once the world's uranium runs out, thorium - and the depleted uranium discharged by the power reactors - could form the "fertile base" for nuclear power generation, the BARC scientists claim in their paper.

They believe their FTBR is one such "candidate" reactor that can produce energy from these two fertile materials with some help from fissile plutonium as a "seed" to start the fire.


By using a judicious mix of "seed" plutonium and fertile zones inside the core, the scientists show theoretically that their design can breed not one but two nuclear fuels - U-233 from thorium and plutonium from depleted uranium - within the same reactor.


This totally novel concept of fertile-to-fissile conversion has prompted its designers to christen their baby the Fast 'Twin' Breeder Reactor.


Their calculations show the sodium-cooled FTBR, while consuming 10.96 tonnes of plutonium to generate 1,000 MW of power, breeds 11.44 tonnes of plutonium and 0.88 tonnes of U-233 in a cycle length of two years.


According to the scientists, their FTBR design exploits the fact that U-233 is a better fissile material than plutonium. Secondly, they were able to maximise the breeding by putting the fertile materials inside the core rather than as a "blanket" surrounding the core as done traditionally.


"At present, there are no internal fertile blankets or fissile breeding zones in power reactors operating in the world," the paper claims.


Praise for the concept


The concept has won praise from nuclear experts elsewhere. "Core heterogeneity is the best way to help high conversion," says Alexis Nuttin, a French nuclear scientist at the LPSC Reactor Physics Group in Grenoble.


Thorium-based fuels and fuel cycles have been used in the past and are being developed in a few countries but are yet to be commercialised.




France is also studying a concept of "molten salt reactor" where the fuel is in liquid form, while the US is considering a gas-cooled reactor using thorium.

McLean, Virginia-based Thorium Power Ltd of the US, has been working with nuclear engineers and scientists of the Kurchatov Institute in Moscow for over a decade to develop designs that can be commercialised.


But BARC's FTBR is claimed to be the first design that truly exploits the concept of "breeding" in a reactor that uses thorium.


The handful of fast breeder reactors (FBRs) in the world - including the one India is building in Kalpakkam near Chennai - use plutonium as fuel.


These breeders have to wait until enough plutonium is accumulated through reprocessing of spent fuel discharged by thermal power reactors that run on uranium.


Herein lies the rub.




India does not have sufficient uranium to build enough thermal reactors to produce the plutonium needed for more FBRs of the Kalpakkam type.


The India-US civilian nuclear deal was expected to enable India import uranium and reprocess spent fuel to recover plutonium for its FBRs. But this deal has hit a roadblock.


"Jagannathan's design is one way of utilising thorium and circumventing the delays in building plutonium-based FBRs," says former BARC director P.K. Iyengar.


Meanwhile, India's 300,000 tonnes of thorium reserves - the third largest in the world - in the beach sands of Kerala and Orissa states are waiting to be tapped.

The BARC scientists say that thorium should be inducted into power reactors when the uranium is still available, rather than after it is exhausted.


But the FTBR still needs an initial inventory of plutonium to kick-start the thorium cycle and eventually to generate electricity. A blanket ban on India re-processing imported uranium - a condition for nuclear cooperation with the US - could make India's thorium programme a non-starter.


Iyengar has one suggestion that he says must be acceptable to the US if it is serious about helping India to solve its energy problem.


"The US and Russia have piles of plutonium from dismantled nuclear weapons," Iyengar told IANS, adding: "They should allow us to borrow this plutonium needed to start our breeders. We can return the material after we breed enough."

France is also studying a concept of "molten salt reactor" where the fuel is in liquid form, while the US is considering a gas-cooled reactor using thorium.

McLean, Virginia-based Thorium Power Ltd of the US, has been working with nuclear engineers and scientists of the Kurchatov Institute in Moscow for over a decade to develop designs that can be commercialised.


But BARC's FTBR is claimed to be the first design that truly exploits the concept of "breeding" in a reactor that uses thorium.


The handful of fast breeder reactors (FBRs) in the world - including the one India is building in Kalpakkam near Chennai - use plutonium as fuel.


These breeders have to wait until enough plutonium is accumulated through reprocessing of spent fuel discharged by thermal power reactors that run on uranium.


Herein lies the rub.




India does not have sufficient uranium to build enough thermal reactors to produce the plutonium needed for more FBRs of the Kalpakkam type.


The India-US civilian nuclear deal was expected to enable India import uranium and reprocess spent fuel to recover plutonium for its FBRs. But this deal has hit a roadblock.


"Jagannathan's design is one way of utilising thorium and circumventing the delays in building plutonium-based FBRs," says former BARC director P.K. Iyengar.


Meanwhile, India's 300,000 tonnes of thorium reserves - the third largest in the world - in the beach sands of Kerala and Orissa states are waiting to be tapped.

The BARC scientists say that thorium should be inducted into power reactors when the uranium is still available, rather than after it is exhausted.


But the FTBR still needs an initial inventory of plutonium to kick-start the thorium cycle and eventually to generate electricity. A blanket ban on India re-processing imported uranium - a condition for nuclear cooperation with the US - could make India's thorium programme a non-starter.


Iyengar has one suggestion that he says must be acceptable to the US if it is serious about helping India to solve its energy problem.


"The US and Russia have piles of plutonium from dismantled nuclear weapons," Iyengar told IANS, adding: "They should allow us to borrow this plutonium needed to start our breeders. We can return the material after we breed enough."

http://content.msn.co.in/News/National/NationalIANS_010707_1736.htm#top
 
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heh we have already designed a bunch of such stuffs, one is a 4th gen reactor without using any coolant pumps, we are designing CHTR to generate Hydrogen as well.
 
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VERY NICE ARTICLE MHUHUAA I LOVE IYENGAR SIR.

"The US and Russia have piles of plutonium from dismantled nuclear weapons," Iyengar told IANS, adding: "They should allow us to borrow this plutonium needed to start our breeders. We can return the material after we breed enough."

I hope this happens ;) Neo do you see the commercial viability now?


I really wanted to know what is the moderator used in this new thorium reactor...aka the 3rd stage of our thorium programme.
 
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IMO I just realised the new reactor designed and stated in the article is different from the above three, perhaps a autonomous one to kick off without any uranium and plutonium inputs, it would be revolutionary if they achieve the same breeder potential if it is a solid core reactor.
 
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heh we have already designed a bunch of such stuffs, one is a 4th gen reactor without using any coolant pumps, we are designing CHTR to generate Hydrogen as well.

Joey,

How can a reactor funtion without coolant pumps? :confused:
Please put some light on it.

Thanks!
 
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Joey,

How can a reactor funtion without coolant pumps? :confused:
Please put some light on it.

Thanks!

What I meant is removable of coolant pumps, IT does not uses coolant pumps but rather uses coolant channels which uses passive measures for transportation instead of pumps, thus avoiding moving parts and increasing safety and decreasing cost.

Check this article here, TS Subramanian is a excellent excellent scientific journalist even though The Hindu is a Communist paper..It will use Passive safety measures and Passive cooling through convection and Gravity.

SPECIAL FEATURE: BARC AT 50

Innovative reactor

T.S. SUBRAMANIAN


The AHWR project enters a crucial phase with the regulatory board completing the pre-licensing appraisal of the reactor's design.




A model of the Advanced Heavy Water Reactor at BARC.



V.V. KRISHNAN


THE construction of India's futuristic Advanced Heavy Water Reactor (AHWR) is expected to begin by the end of 2007, according to Ratan K. Sinha, Director, Reactor Design and Development Group (RD&DG), Bhabha Atomic Research Centre (BARC). The first pour of the concrete will take place in a few months. The reactor will be powered by thorium, described as "the fuel of the future". The 300-MWe AHWR will signal the beginning of the third stage of India's three-stage nuclear power programme. It will use the naturally available thorium and the fissile material, uranium-233, as fuel. Boiling water will be the coolant and heavy water, the moderator.

According to Sinha, although the reactor was initially designed to generate 235 MWe, its capacity has been stepped up "through certain additional innovations and experimentation which helped in optimising the margins". The reactor will also produce 6,00,000 litres of desalinated water a day, which will meet the process requirements of demineralised water of the plant and the drinking water requirements of the plant staff. "This has been a gain in terms of the additional capacity we could envisage through innovations," he said.

The AHWR project has entered a crucial phase with the regulatory body, the Atomic Energy Regulatory Board (AERB), completing the pre-licensing appraisal of the reactor's innovative design. There is a mood of expectation at Engineering Hall No.7 where the RD & DG is located. It was in this hall that several important elements of India's ambitious atomic energy programme took shape. Today, this cavernous hall houses huge engineering facilities, massive robots called refuelling machines, computerised and control rooms, among other things. Keeping a direct tab on the development of the AHWR is Anil Kakodkar.

Homi J. Bhabha envisaged a three-stage programme. The first stage is in commercial domain with 15 PHWRs that use natural uranium as fuel for generating electricity. The second stage, which envisages construction of FBRs, has begun with the construction of the 500-MWe Prototype Fast Breeder Reactor pressing ahead at Kalpakkam. The FBRs will use plutonium-uranium mixed oxide as fuel. Four more FBRs with a capacity of 500 MWe will be built before 2020. In the third stage, reactors using thorium as fuel will be built.

Sinha, who is also the Director, Design, Manufacturing and Automation Group at BARC, argued that although the three-stage programme was conceived five decades ago, it was still valid. Only about 10,000 MWe of nuclear power can be generated with the limited quantity of natural uranium available in the country. Even at the current rate of electricity generation in the world, the known and reasonably assured resources of natural uranium in the world will not last more than 60 years. With a boom in population and the resultant increase in the country's energy requirements, "the bottom line is that we have to reach a thorium-utilisation programme fast", Sinha said.

Besides, "we have plenty of thorium available and that too of good quality," he said. India's three-stage programme with its step-by-step approach acquires relevance because thorium cannot be used straightaway in a reactor to generate electricity.

"We cannot use thorium alone as a fuel in a reactor like we do with natural uranium," explained Sinha. Unlike natural uranium, thorium does not have any fissionable isotopes. Unlike thorium, uranium-233 does not occur in nature as a constituent of natural uranium. Thorium has to be used in some other system (reactor) to convert it into uranium-233. The AHWR will use thorium as feed and convert it into fissile uranium-233, which will then undergo fission in situ to generate electricity. The AHWR will also use a small amount of plutonium.

But small quantities of plutonium reprocessed from the PHWRs alone will not be sufficient to support a big electricity-generation programme that will use large quantities of thorium. It is here that the relevance of the FBRs comes in. The breeder reactors will breed not only enough plutonium but can convert thorium into uranium-233.

"So we need the Fast Breeder Reactors... Since we cannot wait for the FBRs to produce uranium-233, we first want to use the plutonium produced from the PHWRs for the demonstration of new technologies relevant for the third stage. That is why we are going in for the AHWR," explained Sinha.

Its design has several innovative features. The AHWR will employ what are called passive safety features. According to a DAE note, these features will "achieve the conflicting goals of safety and economy".

The reactor will have no pumps and there will be no moving parts. "It neither depends on help from instrumentation nor relies on control mechanism," the note says. Passive safety depends on natural phenomena such as gravity, natural convection and stored energy.

The note says: "The AHWR will be one of the first-ever power reactors employing natural circulation, also known as thermo-siphoning, for cooling of the reactor core under all conditions."

Elimination of major equipment such as coolant pumps, driving motors and power equipment will cut down the plant cost. In the case of an accident, water stored in a huge overhead tank inside the reactor building will ensure core cooling for three full days, without any human intervention. Besides, the safety of the reactor will not depend on the operator's actions alone. The reactor will have three shut-down systems, including one to take care of postulated `insider threat' scenario.

Although the AHWR will be built in the near-term, the technologies in the reactor will be relevant for an entire era when thorium will be the fuel for a generation of reactors. Since the innovations will have a bearing on the safety of the reactor.

BARC felt it necessary to have the new safety features reviewed by the AERB under the pre-licensing safety reviews. Moreover, these safety features were not addressed by the existing system of regulatory documents, codes and guides that were prepared for the current generation of reactors.

Sinha said: "The design has many first-of-its-kind features. It has no pumps. The fuel itself is of a new kind. So we felt that our regulatory authorities should have a good look at some of these unique features and help us to know whether more validations are needed and whether we should do more R&D. For the past year and a half, the AERB has been having a good look at the design... Various safety features have been discussed. Deviations from the existing [safety] practices of the current generation of reactors have been examined in great detail."

The safety review committee concluded that the reactor's safety features were adequate for the reactor to go up for a formal licensing process.

The DAE is going ahead with further design validations of this reactor. A large experimental facility has been built in Engineering Hall No.7 so that RD & DG personnel could simulate, on a full scale, conditions that will prevail under various normal operations and postulated events of different kinds. This will help in validating the computer codes, which were originally used in designing such large-scale experiments. Such codes have been validated for small-scale experiments.
http://www.hinduonnet.com/fline/fl2408/stories/20070504003210600.htm

More Information here,

http://www.npcil.nic.in/nupower_vol13_3/ahwr.htm
http://www.barc.ernet.in/webpages/organization/hw_rnd_homepage/mod_rddgact/mainprog/ahwr-d.htm

From BARC Website,

AHWR Coolant Channel Assembly

Advanced Heavy Water Reactor (AHWR) Coolant Channel is a vertical channel and around 14 meter long. The fuel assembly is housed inside the coolant channel within the active length of 3.5M. The de-mineralised light water at 73kg/cm 2 and 270oC enters from the lower end of the channel and leaves the coolant channel from top end as steam-water mixture (14 to 16% Boiling) at 285oC.

The Coolant Channel consists mainly of central Zr2.5%Nb pressure tube extended beyond the core by stainless steel end fittings The fuel is housed inside the central Zr2.5%Nb pressure tube. The portion of the pressure tube housing the fuel assembly is having a uniform bore of 120mm. Below the fuel assembly location, the pressure tube reduces to 91 mm OD. The maximum OD of the bottom end fitting is 130mm so that it could pass through the bore of the top end fitting. This helps in single channel re-tubing easier and in a shorter duration than in PHWR, and could be done during a normal shut down without any elaborate preparations. Even large scale re-tubing is also expected to take much less time than in PHWR. The channel facilitates direct injection of emergency core cooling system (ECCS) water directly to hot fuel pins the event of a loss of coolant accident (LOCA), thus making ECCS more effective.

From NPCIL website,

The AHWR incorporates several passive safety features. These include:

Core heat removal through natural circulation, direct injection of Emergency Core Coolant System (ECCS) water in fuel.

Passive systems for containment cooling and isolation, and

Availability of a large inventory of borated water in overhead Gravity Driven Water Pool (GDWP) to facilitate sustenance of core decay heat removal, Emergency Core Cooling System (ECCS) injection and containment cooling for three days without invoking any active systems or operator action.
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During normal reactor operation, full reactor power is removed by natural circulation caused by thermosyphoning phenomenon. Primary circulation pumps are eliminated and the necessary flow rate is achieved by locating the steam drums at a suitable height above the center of the core, taking advantage of the reactor building height.The steam-water mixture from each coolant channel is led through 125 mm NB tail pipes to four steam drums, which are located with an elevation difference of 39 m with respect to inlet feeder (coolant channel bottom). The steam at a pressure of 70 kg/cm2 is separated from the steam-water mixture in steam drums. The steam is led to turbine by two 400 mm NB pipes. The steam from the turbine is condensed and after purification of the condensate and preheating, it is pumped back to the steam drums at a temperature of 165°C. The feed water is mixed with the water separated from steam-water mixture at 285°C in the steam drums. The water level in the steam drum is a function of reactor power and is maintained at a set level during power operation.

Cheers!
 
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