Nuclear power of russia - 50 years of history

The fifth nuclear power plant of Russia was Novovoronezh NPP.Beginning of the works in the Laboratory № 2 on the pressurized water reactor design dated from the year of 1951. The first unit of the Novovoronezh NPP with the rated power of 210 ООО kW was put into operation in September 1964. That was a new-type pressurized water reactor with the output of 760 ООО kW. The reactor was installed in a cylindrical steel vessel with the wall thickness of 100 mm, diameter-3,8 m and height - 11,2 m.

The Novovoronezh NPP became a testing area for the vessel type reactors. In December 1969, the second power unit was commissioned at Novovoronezh, its capacity was 365 MW. The core dimensions were kept unchanged. There were 348 fuel assemblies in the reactor core. In December 1971, the third unit with V-230 reactor was commissioned, its electric capacity being 440 MW, thermal capacity - 1 370 MW. Since then, reactors of that type were extensively implemented in Russia and abroad.

Further improved reactor model was the V-213 design. It was a progressive step with respect to nuclear safety. The building design provided for arrangement of the special steam absorbers in case of the primary circuit main pipe rupture. For each VVER-440 reactor, twо 220 MW turbines were provided.

VVER-440 plants were built in Bulgaria, East Germany, Hungary, Finland, Czechoslovakia, and were under construction in Cuba.

Novovoronezh-4 of 440 MW was put into operation in the year of 1972, and the fifth power unit of the electrical output 1 ООО MW was commissioned in 1980. This was the first one from a next series of the V-338 reactors. The reactor was provided with only one turbine.

The sixth Russian NPP was Dimitrovgrad NPP. The B0R-60 reactor that was started construction of in the year of 1965, it was commissioned in 1968 at the Research Institute for Nuclear Reactors. At first, this was an experimental plant with the fast neutron reactor of 60 MW(th) and 12 MW(e), and the plant gradually changed into a permanent source of electricity and heat for the Institute and town. The reactor coolant was sodium, whose temperature at the reactor outlet was 600 °C. 150 kg of 90 % enriched uranium was used as fuel.

The plant was a prototype for BN-350 fast breeders in the city of Shevtchenko and for the BN-600 of the Beloyarsk NPP; it had two sodium circuits and one external water circuit. The B0R-60 flow diagram includes two different-type steam generators and two turbines.

The seventh plant of Russia was Kola NPP.The plant consists of four VVER-440 reactors where two reactors are of the V-230 design and other two reactors - of the V-213 design. Kola-1 was put into operation on 29 June, 1973, Kola-2 - on 9 December, 1974, Kola-3 - on 24 March, 1981, and Kola-4 - on 11 October, 1984.

The eighth nuclear power plant of Russia was Leningrad NPP.The plant includes four RBMK-type reactors of 1 ООО MWe each. The first unit was put into operation in December 1973, the second one - at the end of the year of 1975, the third one - in 1979, the fourth one - in 1981. Each RBMK- type generates steam for two turbo-generators having the K-500-65 turbine of the capacity of 500 MW. The thermal output of the RBMK-type reactor is 3 200 MW. Reactors of this type are characterized by relatively low efficiency.

The Leningrad RBMK-type reactors were initially designed ( in 1963) as dual- purpose reactors for production of plutonium and electrical power but in the year of 1967 the Leningrad terms of reference and design were modified, and the RBMK-type reactor had only the power generation function.

The reactor has 1 700 channels with fuel assemblies. Each channel houses 2 assemblies, each containing 18 fuel elements. After the Leningrad NPP the RBMK- type reactors were used in Kursk, Smolensk and Chernobyl plants.

2 Переведите на русский язык следующие английские словосочетания:

1) pressurized water reactor;

2) the rated power;

3) to put into operation;

4) to install the reactor;

5) the vessel type reactors;

6) the reactor core;

7) fuel assemblies;

8) nuclear safety;

9) the fast neutron reactor;

10) steam absorbers.

3. Найдите в тексте английские эквиваленты следующих словосочетаний:

1) тепловая мощность;

2) постоянный источник;

3) обогащённый уран;

4) парогенератор;

5) турбогенератор;

6) атомная станция;

7) производство плутония;

8) электроэнергия;

9) атомный реактор;

10) четвёртый энергоблок.

3 Найдите в тексте слова, имеющие общий корень с данными словами. Определите, к какой части речи они относятся, и переведите их на русский язык:

1) pressure; 2) to operate;

3) cylinder; 4) thick;

5) to change; 6) to extend;

7) to arrange; 8) to absorb;

9) to generate; 10) to produce.

5 Задайте к данному предложению все типы вопросов (общий, альтернативный, разделительный, специальный: а) к подлежащему, б) к второстепенному члену предложения).

The first unit of the Novovoronezh NPP with the rated power of 210 ООО kW was put into operation in September 1964.

6 Выполните анализ данных предложений, обратив внимание на следующие грамматические явления: формы и функции инфинитива, инфинитивные конструкции (сложное дополнение, подлежащее), существительное в роли определения, функции слов one (ones), that (those), условные предложения:

1) Beginning of the works in the Laboratory № 2 on the pressurized water reactor design dated from the year of 1951.

2) That was a new-type pressurized water reactor with the output of 760 ООО kW.

3) The Novovoronezh NPP became a testing area for the vessel type reactors.

4) Novovoronezh-4 of 440 MW was put into operation in the year of 1972, and the fifth power unit of the electrical output 1 ООО MW was commissioned in 1980. This was the first one from a next series of the V-338 reactors.

5) Each RBMK- type generates steam for two turbo-generators having the K-500-65 turbine of the capacity of 500 MW.

6) Further improved reactor model was the V-213 design.

7) Each channel houses 2 assemblies, each containing 18 fuel elements.

7)Ответьте на вопросы по тексту:

1) What kind of NPP did The Novovoronezh NPP become ?

2) In what countries were VVER-440 plants built ?

3) Where was the sixth Russian NPP constructed ?

4) How many VVER-440 reactors does the seventh plant of Russia, Kola NPP plant, consist of?

5) Where is the eighth nuclear power plant of Russia ?

6) How many RBMK-type reactors does Leningrad NPP include ?

7) Where else (at what NPP )were the RBMK- type reactors used ?