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High Fissile Fuel in Nuclear Submarine Lasts LongQuote:
BARC designed, developed and built the steam generating unit of Arihant by facing many technical challenges
“The compact Pressurized Water Reactor was designed for this purpose with several features; such as very quick response for power ramping, extremely stable undership motions and resistance against exposure to very high acceleration resulting from eventual depth charges”, Dr Sukumar Banerjee, Director, BARC said in his Founder’s Day Address
“Since the nuclear reactor is fuelled with high fissile containing fuel, it can supply energy in the submerged condition for an extended period without refuelling”, he clarified. Details about the reactor are classified.
Generally, Pressurized Water Reactors (PWR) power nuclear submarines. A PWR has a core of highly enriched uranium. When uranium nuclei undergo fission, the fission fragments carry enormous energy. They dissipate the energy in the core which gets heated up. The high pressure primary system with water as coolant removes the heat from the core continuously.
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The reactor internals remain inaccessible for inspection or replacement throughout the long life of their core. They must be rugged and resilient. Reactor components and systems must withstand, harsh and hostile environment, long term effects of radiation, corrosion, high temperature and pressure.
It is very nice to see BARC talking openly about the Naval reactor and proudly so. Naturally when India was considered to be of having no prior experience in the construction of Naval reactos, everyone tends to agree with the perception that it could be a Russian reactor. Influential people like Adm. Arun Prakash talk about the reactor could be of Charlie class 2nd generation reactor or on the basis of that.
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The nuclear reactor installed on the S-2, according to open source information, is understood to be based on first or second generation Soviet era technology with a short re-fuelling cycle.
That made me wonder how to reconcile this with the statement from Banerjee.
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Srikumar Banerjee, BARC Director, also stressed that “the event marks the beginning of PWR technology in India.” The BARC made many design features to make this reactor compact. “There are novelties not only in the reactor’s design but in its manufacturing,” he said. For instance, the steam generator which drove the turbine to generate electricity, was compacted in a novel manner. The heart of the reactor is the steam generator.
Russian reactor reference:Quote:
Second generation reactors
Experience from the first generation reactors showed that the main operational problem was leakage of water from the primary to the secondary circuit. This occurred mainly through the steam generators. There were also problems of leaks in the pumping systems and the gaskets of the steam generators. The pumps and steam generators were intended to cool the reactor in the event of a power failure.
These experiences formed the basis for modifications introduced in the second generation reactors. Nevertheless, the loop pattern (i.e., a system of spiralling cooling pipes) was retained. The volume and distribution of the primary circuit was sharply reduced, and a system of pipes within pipes was used for the steam generators, especially for the newest pumps leading to the primary circuit.
Third generation reactors
A new block system was developed to protect the cooling circuits from leakage. By replacing the old system of pipes with a block system, in which the reactor and the cooling system were treated as one block, the dimensions of the pipes and other components could be reduced because the cooling efficiency of the system could be increased.
From a safety point of view, this solved number of problems. First of all, this system permitted a natural circulation of coolant within the primary circuit, even at high power. This was important for the flow of coolant into the reactor core at complete or partial power failure. With the block system, pipes to the primary circuit were replaced with short, wide diameter pipes which connected the main components (reactor, steam generators, and pumps).
Fourth generation reactors
The reactor for the first submarine was finished in 1995. Fourth generation nuclear reactors are formed into a single block. The monoblock design has the advantages of localising the coolant in the primary circuit into one volume of fluid and eliminates the need for pipes of wide diameter. The fourth generation reactors are constructed consistent with modern requirements for radiation safety.