Studies in the physics of fast neutron reactors

Leipunskii, A.I.; Abramov, A.I.; Andreev, V.N.; Барышников, А. Ю.; Bondarenko, I. I.; Galkov, V. I.; Golubev, V. I.; Gul'ko, A.D.; Guseinov, A. G.; Kazachkovskii, O. D.; Kozlova, N. V.; Krasnoiarov, N. V.; Kuz'minov, B.D.; Морозов, В. Н.; Nikolaev, M.N.; Smirenkin, G.N.; Stavisskii, Iu. Ia.; Ukraintsev, F.I.; Usachev, L.N.; Fetisov, N.I.; Sherman, L. E.

doi:10.1007/bf01472483

Cited by 5 publications

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“…[1,2]. The radiological (biological) shielding of BR-2 turned out to be excessive; measurements and analysis of its characteristics made a substantial contribution to the knowledge needed to perform calculations of other experimental and power fast reactors.…”

Section: Years After the Start-up Of Br-2 -The First Fast Reactor In mentioning

confidence: 99%

50 years after the start-up of BR-2 — The first fast reactor in Europe

2006

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is the 50th anniversary of the start-up of the first fast reactor in Europe -the BR-2. This was an important step in the development of fast reactors for nucler power production. Experience in operating a core under conditions with cramped bundles of fuel elements and a liquid-metal coolant with heat flows through the surface of the claddings of about 1.2·10 6 kJ/(m 2 ·h) was gained for the first time on the BR-2 reactor. Investigations performed on the BR-2 of the breeding ratio showed that BR = 1.8 ± 0.3. The first experience of physical start-up of a fast reactor, determining the efficiency of the reactivity control organs and their calibration, was gained.On February 14, 2006, fifty years passed from the day that the first fast reactor BR-2 in Europe was put into operation [1, 2] -an important step in the development of fast reactors for nuclear power production. To understand the significance of this event, it is necessary to know to what this path has now led and what it promises for the future.The study of the prospects for the commercial production of fast reactors started in our country in 1949 under the direction of A. I. Leipunskii [3]. The main stimulus to the development of this direction was the possibility of expanding the fuel base of future nuclear power by a factor of 50 or more as a result of the fact that the energy in a fast reactor is produced as a result of the fissioning of plutonium formed from the main natural isotope of uranium 238 U, which does not fission in the fuel spectrum and which is present in a quantity 140 times greater than 235 U. Excess plutonium is generated in a fast reactor, and this plutonium can be used as a catalyst for new fast reactors, thereby allowing for the development of nuclear power at the required rates. In contrast to thermal reactors, which burn 235 U, the fuel-breeding ratio in fast reactors can be appreciably greater than 1, which is what makes it possible to use all the natural uranium as the raw material for power generation.The search for and validation of the optimal solutions (choice of fuel, coolant, structural materials, arrangement of the reactor, and others) during the last 60 years has been crowned with the start-up and long-time operation of the experimental reactors BR-5 and BOR-60 and the power reactors BN-350 and -600 with sodium coolant [4]. Domestic experience in operating fast reactors now exceeds 130 reactor-years.All reactors have demonstrated a high level of operational safety. The negative temperature and power coefficients of reactivity ensure self-regulation of the reactors. The energy distribution in the core is stable. The reactors can be easily controlled. Heat removal by sodium is effective; the temperature margin up to boiling of the sodium in the core during reactor operation at full power is at least 300°C. The low pressure of sodium in the absence of appreciable corrosion phenomena in it facilitates the sealing of the loops. Sodium leaks, which occur initially, were eliminated by specially developed means. On the whole, the ...

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Section: Years After the Start-up Of Br-2 -The First Fast Reactor In mentioning

confidence: 99%

50 years after the start-up of BR-2 — The first fast reactor in Europe

2006

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“…(25) The BR-1 zero-power reactor has a small Pu core with either a depleted uranium or a copper reflector. Reported investigations with this facility were confined to criticality, cross sections, and flux-distribution phenomena.…”

Section: E-specific Reactor Systemsmentioning

confidence: 99%