Вариант 8

1. Прочитайте и переведите текст:

THE DEVELOPMENT OF FAST REACTORS IN RUSSIA.

Today it is generally recognized that the future development of nuclear power is inseparably connected with nuclear tech­nologies based upon fast reactors and closed fuel cycles, including the processing of spent fuel and recycling both the pro­duced plutonium and the most long-living radioactive waste.

That is why "The Strategy of Nuclear Power Development in Russia in the First Half of the XXIst Century" gave the prefer­ence to the construction of fast reactors with sodium coolant. Generation IV Program (GIF) has also chosen to develop this power production technology as the most promis­ing one.

Fast reactors with sodium coolant have been developing since the 1940-ties and by now this technology has successfully demonstrated its advantages that were revealed during the first stage of its devel­opment: good serviceability and reliable safe operation. Effective operation of Russian fast reactors BN-350, 250 MW, (1972-1997) and BN-600, 600 MW, (1980-present time) during the last 25 years is a very representing reference.

Now the specialists are seeking to raise economic competitiveness of the reactors of this type and focus their attention on the development of production processes with a closed fuel cycle. A very important role in this work is to be played by the new unit with BN-800 reactor that is under construction now at Beloyarsk NPP (the fourth unit). The construction of the reactor is the nearest and a necessary stage in the development of fast reactors in Russia.

The implementation of BN-800 project is meant to meet the nuclear power chal­lenges of the XXIst century, including the non-proliferation demand.

The development of fast reactors and experience of their operation in Russia. By now only sodium technology has been realized in practice and continues its devel­opment. The most impressive results in the development of fast sodium reactors have been achieved in Russia. The total operat­ing time of fast reactors in the whole world impressive results in the development of fast sodium reactors have been achieved in Russia. The total operat­ing time of fast reactors in the whole world is 270 reactor years, 125 out of them -in Russia.

BR-5/10 in Obninsk was effectively oper­ating for 43 years and was shut down in 2002 only because the majority of experi­mental activities had been transferred to BOR-60, the reactor that had been operat­ing by that time for 35 years as well. BN-350 reactor operated flawlessly for 25 years though its designed lifetime was 20 years. Full-scale accounting of the development and experience of operating the demonstra­tion NPP enabled a unique pilot project of the first commercial experimental NPP with integrated reactor BN-600.

This reactor commissioned in 1980 at Beloyarsk NPP as a part of its Unit 3 has shown high safety and reliability character­istics. Average value of the load factor of the unit taken for 22 years (after the unit output was brought to its designed figures in 1982) is 74%. The frequency of scrams in the last decade was considerably less than at the reactors of other types both in Russia and abroad (once in 3 years in average). Operating experience of the reactor includes unique data on sodium leakages and demonstrates the efficiency of protec­tion systems for isolating fire sources and restricting radioactivity releases into atmos­phere. The process of operating domestic fast reactors allowed to establish approved procedures of equipment maintenance, repair and replacement, including such bulky pieces as pumps and steam genera­tors.

The experience of operating the first reactors BR-5 (10), BOR-60, BN-350 and BN-600 makes it possible to start the sub­stantiating of BN-600 lifetime extension up to 40-45 years against the designed 30 years.

The development program for fast reac­tors in Russia is based upon the established experimental, designing and industrial foun­dation. Experimental basis comprises a combination of complex test units and stands for the investigation of physical, thermo hydraulic, material and production process properties (at the Institute of Physics and Power Engineering -IPPE); test units for investigating fuel compositions and radiation materials studies (VNIINM, IRM, NIIAR, IPPE); stands for testing equipment and conducting safety research work: (IPPE, OKBM) and the experimental sodium fast reactor BOR-60 (NIIAR). Research an designing base is formed by the highly qualified personnel of the research institute (IPPE, NIIAR, VNIINM), designing bureau (OKBM, OKB "Gidropress") and project developing institutions (AEP in St Petersburg, VNIPIET).

The enterprises that have experience and well-developed technologies for the production of fast reactor equipment (OKBM, ZIO LMZ, "Elektrosila" Manufacturers, "Proletarsky Zavod" and others) constitute the industrial base of this project.

Positive experience accumulated in the spheres of development and operation of fast reactors provides evidence that this well-elaborated technology has actually become a usual practice in Russia, and its safety and reliability meet all the require­ments of the future nuclear technologies.

BN-800 project naturally continues the development of sodium fast reactors in Russia. The background of the project is formed by the designing and operating experience of sodium fast reactors of three generations. BN-800 project is first of all based upon the technical solutions tested and approved during the construction and operation of the previous BN-600 reactor. To substantiate the project a great number of experiments and tests were made both at test units, stands and on operating reactors. It is clear that in the process of the project development the input from the operating experience on the whole was taken into consideration as well as all the changes in the regulations, norms and standards (especially after the Chernobyl accident).

Reactor installation BN-800 comprises fast neutron reactor with thermal capacity 2,100 MW, three coolant circulation loops of the primary circuit, three circulation loops of the secondary circuit and three steam gen­erators "sodium-water" of module section type.

2. Переведите на русский язык следующие английские словосочетания:

1. fast neutron reactor ; 6. long-living radioactive waste;

2. technical solutions; 7. the processing of spent fuel;

3. nuclear technologies; 8. sodium coolant;

4. sodium leakage; 9. to raise economic competitiveness;

5. a closed fuel cycle; 10. highly qualified personnel

3. Найдите в тексте английские эквиваленты следующих словосочетаний:

1.ядерные технологии; 6. обработка отработанного топлива;

2. отдавать предпочтение; 7. натриевый охладитель;

3. замкнутый топливный цикл; 8. решать задачи ядерной энергии;

4. реактор быстрых нейтронов; 9. надежная безопасная эксплуатация;

5. утечка натрия; 10. частота аварий.

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

1. high 6. design

2. leak 7. compete

3. process 8. cycle

4. react 9. impress

5. regulate 10. prefer­

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

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

1. Generation IV Program (GIF) has also chosen to develop this power production technology as the most promis­ing one.

2. Now the specialists are seeking to raise economic competitiveness of the reactors of this type.

3. The implementation of BN-800 project is meant to meet the nuclear power chal­lenges of the XXIst century.

4. The process of operating domestic fast reactors allowed to establish approved procedures of equipment maintenance.

5. To substantiate the project a great number of experiments and tests were made both at test units, stands and on operating reactors.