Problems of BN-800 construction and the possibilities of developing advanced fast reactors

The development and operation of sodium-cooled fast reactors and the prospects for developing the next generation of such reactors are reviewed. The main phases, the problems of each phase, and the results obtained by solving these problems are shown. The main results obtained by adopting innovative technical design solutions, making it possible to consider the problem of developing a competitive power-generating unit with a BN-1200 reactor, are examined and described.

Section: Transfer From the Secondary Loop Arrangement Of The First Lomentioning

confidence: 99%

Successive development phases for sodium-cooled fast reactors

Bagdasarov

Kamaev

2012

“…The experience gained in operating the BN-600 reactor is of scientific and practical interest [1][2][3][4][5][6][7][8]. The design of the commercial BN-600 power-generating unit incorporates the positive experience accumulated in our country in the development, construction, and operation of preceding facilities with sodium-cooled fast reactors -BR-5/BR-10, BOR-60, and BN-350.…”

mentioning

confidence: 99%

30 Years of experience in operating the BN-600 sodium-cooled fast reactor

Ошканов

Saraev

Bakanov³

et al. 2010

Self Cite

Experience in operating the BN-600 sodium-cooled fast reactor during its nominal service life as well as its service life extension period, an additional 15 years, is described. Information is presented on the performance indicators which were achieved and deviations from the normal operating regime which occurred when the reactor was first started up. The degree to which they affect the safety and technicaleconomic performance of the facility is evaluated. It is concluded on the basis of an analysis of the BN-600 operating experience that sodium-cooled fast reactors have now been mastered commercially and that their prospects for further development are good.April 8, 2010 marks 30 years since power startup of the No. 3 unit of the Beloyarskaya nuclear power plant with the BN-600 reactor. This reactor is the only such power reactor operating in the world at the present time. Moreover, this is the first commercial power-generating unit with a sodium-cooled fast reactor operating in a commercial regime anywhere in the world.The successful operation of the BN-600 reactor is confirmation of the leading position that our country now enjoys in the field of sodium-cooled fast reactors. The completion of the nominal operating period of the power-generation unit, equal to 30 years, is an important milestone, a time for summing up the operation and determining the future prospects of the BN-600 reactor itself and the direction as a whole.BN-600 Operation during the Nominal Service Period. The experience gained in operating the BN-600 reactor is of scientific and practical interest [1][2][3][4][5][6][7][8]. The design of the commercial BN-600 power-generating unit incorporates the positive experience accumulated in our country in the development, construction, and operation of preceding facilities with sodium-cooled fast reactors -BR-5/BR-10, BOR-60, and BN-350. Problems which became apparent during the initial period of mastering this reactor technology were also taken into account in the development of the BN-600 design; therefore BN-600 can be viewed as the next step in the development and realization at the commercial level of sodium-cooled fast reactors.

“…The approach to the development of the equipment is based on maximum use of the experience gained in operating BN-350 and -600 as well as experience in developing the BN-800 design, which gives a basis for ensuring reliable operation of the BN-1200 equipment. New solutions for improving the technical-economic indicators and increasing the safety of a power-generating unit, whose validation required R&D work, are examined at the same time.The operation of BN-350 and -600 as well as the development of the BN-800 design made it possible to accumulate a great deal of experience in developing and operating the entire system of equipment used in fast-neutron nuclear facilities [1][2][3]. For this reason, the possible technical solutions directed toward improving the equipment in order to improve safety and the technical-economic indicators of the next-generation facility BN-1200 are chosen on the basis of an analysis of the experience gained in developing and operating fast-neutron reactors taking account of the required R&D work.…”

mentioning

confidence: 99%

“…The operation of BN-350 and -600 as well as the development of the BN-800 design made it possible to accumulate a great deal of experience in developing and operating the entire system of equipment used in fast-neutron nuclear facilities [1][2][3]. For this reason, the possible technical solutions directed toward improving the equipment in order to improve safety and the technical-economic indicators of the next-generation facility BN-1200 are chosen on the basis of an analysis of the experience gained in developing and operating fast-neutron reactors taking account of the required R&D work.…”

mentioning

confidence: 99%

Improvement of the equipment in fast-neutron reactor facilities

Vasiliev¹,

Kamanin²,

Gladkov³

et al. 2010

Information is presented on the development of the main equipment of the BN-1200 advanced reactor facility: first-and second-loop main circulation pumps, intermediate heat exchanger, actuation mechanism of the cold filter-trap control and protection system, autonomous and air heat exchangers, steam generator. The approach to the development of the equipment is based on maximum use of the experience gained in operating BN-350 and -600 as well as experience in developing the BN-800 design, which gives a basis for ensuring reliable operation of the BN-1200 equipment. New solutions for improving the technical-economic indicators and increasing the safety of a power-generating unit, whose validation required R&D work, are examined at the same time.The operation of BN-350 and -600 as well as the development of the BN-800 design made it possible to accumulate a great deal of experience in developing and operating the entire system of equipment used in fast-neutron nuclear facilities [1][2][3]. For this reason, the possible technical solutions directed toward improving the equipment in order to improve safety and the technical-economic indicators of the next-generation facility BN-1200 are chosen on the basis of an analysis of the experience gained in developing and operating fast-neutron reactors taking account of the required R&D work.First-and Second-Loop Main Circulation Pumps. The designs of MCP-1 and -2 for BN-800, -1200 are based on solutions checked in the course of operation over a long period of time as part of BN-600. Structurally, MCP-1 in BN-1200 is an immersible centrifugal vertical one-step pump with bilateral intake with a bottom hydrostatic bearing (Fig. 1a).In developing MCP-1 for BN-1200 higher, as compared with MCP in BN-600 and -800, service life indicators and mass/size characteristics must be attained. Many years of operation made it possible to determine the factors that limit the service life. The main factor is cavitation-erosion wear of the blades in the working wheels. To develop MCP-1 for BN-1200, satisfying the requirements, different structural variants with different rotation rate of the rotor and different structural implementation of the working wheels and guiding apparatus are being developed. This work will increase the service life of the working wheels from 4.5 (MCP-1 BN-800) to 16 years.The design of MCP-2 BN-1200 is based on the solutions checked over long-term operation of MCP-2 BN-600. The operationally confirmed service life characteristics of MCP-2 BN-600 are close the values required for MCP-2 in BN-1200 -14.4 and 16 years, respectively.