Russia Wants to Team Up With India on Fast-Neutron Reactor Project

 

Moscow has invited New Delhi to participate in its fast-reactor research project, according to a Rosatom representative

The construction of the multiobjective fast research reactor, also known by the Russian acronym MBIR, began last year at the Research Institute of Atomic Reactors in Dimitrovgrad, in Ulyanovsk region.

The project is part of a state-run program aimed at creating another technological stage for atomic energy on the basis of the shut fuel cycle with fast neutron reactors, according to Alexander Zagornov, project administrator at Russia’s state atomic energy corporation Rosatom. Zagornov, who was invited to the opening of the company’s South Asia regional center in India, explained that the new development will help neutralize the major ecological issue of deactivating and processing radioactive waste, as the shut fuel cycle includes reusing the waste as new fuel.

“Transition to the closed fuel cycle, which is based on the fast neutron reactors, will lead to the solution of the five key problems — safety, competitiveness, shortage of fuel, reprocessing and refabricating the used nuclear fuel and radioactive waste — as well as in enforcing non-proliferation of fission materials and weapons technologies,” Zagornov told IANS.

He added that, judging by the pattern of the fast research reactors advancement, MBIR could become world’s most powerful facility by 2025. And given that such a unique institution with the high neutron flux cannot be realized on a small scale, a high cost is inevitable.

The best solution, Zagornov said, is regional “collective use centers,” in which one reactor can be used by numerous international clients, adding that Rosatom invites its Indian partners to join in and become pioneers in further research into nuclear processes.

Source: https://sputniknews.com/world/201611011046939036-mbir-fast-reactor/


A fast neutron reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons. Such a reactor needs no neutron moderator, but must use fuelthat is relatively rich in fissile material when compared to that required for a thermal reactor.

Advantages

Fast neutron reactors can reduce the total radiotoxicity of nuclear waste, and dramatically reduce the waste’s lifetime. They can also use all or almost all of the fuel in the waste. Fast neutrons have an advantage in the transmutation of nuclear waste. With fast neutrons, the ratio between splitting and the capture of neutrons of plutonium or minor actinide is often larger than when the neutrons are slower, at thermal or near-thermal “epithermal” speeds. The transmuted odd-numbered actinides (e.g. from Pu-240 to Pu-241) split more easily. After they split, the actinides become a pair of “fission products.” These elements have less total radiotoxicity. Since disposal of the fission products is dominated by the most radiotoxic fission product, cesium-137, which has a half life of 30.1 years, the result is to reduce nuclear waste lifetimes from tens of millennia (from transuranic isotopes) to a few centuries. The processes are not perfect, but the remaining transuranics are reduced from a significant problem to a tiny percentage of the total waste, because most transuranics can be used as fuel.

  • Fast reactors technically solve the “fuel shortage” argument against uranium-fueled reactors without assuming unexplored reserves, or extraction from dilute sources such as ordinary granite or the ocean. They permit nuclear fuels to be bred from almost all the actinides, including known, abundant sources of depleted uranium and thorium, and light water reactor wastes. On average, more neutrons per fission are produced from fissions caused by fast neutrons than from those caused by thermal neutrons. This results in a larger surplus of neutrons beyond those required to sustain the chain reaction. These neutrons can be used to produce extra fuel, or to transmute long half-life waste to less troublesome isotopes, such as was done at the Phénix reactor in Marcoule in France, or some can be used for each purpose. Though conventional thermal reactors also produce excess neutrons, fast reactors can produce enough of them to breed more fuel than they consume. Such designs are known as fast breeder reactors.[citation needed]
  • The fast reactor doesn’t just transmute the inconvenient even-numbered transuranic elements (notably Pu-240 and U-238). It transmutes them, and then fissions them for power, so that these former wastes would actually become valuable.[citation needed]

Disadvantages

  • Breeder reactors are costly to build and operate, and are not likely to be cost-competitive with thermal reactors unless the price of uranium increases dramatically.
  • Due to the low cross sections of most materials at high neutron energies, critical mass in a fast reactor is much higher than a thermal reactor. In practice, this means significantly higher enrichment: >20% enrichment in a fast reactor compared to <5% enrichment in typical thermal reactors. This raises greater nuclear proliferation and nuclear security issues.
  • Sodium is often used as a coolant in fast reactors, because it does not moderate neutron speeds much and has a high heat capacity. However, it burns and foams in air. It has caused difficulties in reactors (e.g. USS Seawolf (SSN-575), Monju), although some sodium-cooled fast reactors have operated safely (notably the Superphénix and EBR-II for 30 years).
  • Since liquid metals have low moderating power and ratio and no other moderator is present, the primary interaction of neutrons with liquid metal coolants is the (n,gamma) reaction, which induces radioactivity in the coolant. Boiling in the coolant, e.g. in an accident, would reduce coolant density and thus the absorption rate, such that the reactor has a positive void coefficient, which is dangerous and undesirable from a safety and accident standpoint. This can be avoided with a gas cooled reactor, since voids do not form in such a reactor during an accident; however, activation in the coolant remains a problem. A helium-cooled reactor would avoid this, since the elastic scattering and total cross sections are approximately equal, i.e. there are very few (n,gamma) reactions in the coolant and the low density of helium at typical operating conditions means that the amount neutrons have few interactions with coolant.

Source: https://en.wikipedia.org/wiki/Fast-neutron_reactor

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