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Karpov, A. V.; Kononyuk, M. Kh.; Mamaev, L.I.; Kulikov, Yu. L.

doi:10.1023/a:1014274009267

Cited by 13 publications

(1 citation statement)

References 2 publications

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“…Prediction of carburization or decarburization of an austenitic stainless steel when exposed to sodium is significant since changes in mechanical properties due to carbon diffusion have been reported by many [21,[38][39][40]. Although the model presented here is with respect to carburization of austenitic stainless steel when exposed to sodium, it can be applied to any diffusion process where the diffusing species undergoes chemical reaction with another constituent element.…”

Section: Regionmentioning

confidence: 99%

Carburization behavior of AISI 316LN austenitic stainless steel – Experimental studies and modeling

Sudha

Bharasi

Anand

et al. 2010

Journal of Nuclear Materials

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Section: Regionmentioning

confidence: 99%

Carburization behavior of AISI 316LN austenitic stainless steel – Experimental studies and modeling

Sudha

Bharasi

Anand

et al. 2010

Journal of Nuclear Materials

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

Kostin¹,

Vasil’ev²

2007

At Energy

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The design features and construction status of the BN-800 reactor being built at the Beloyarskaya nuclear power plant and the main scientific and technical problems which will be solved with the construction of this reactor are examined. The most important ones are mastering a closed fuel cycle, checking new technical solutions, and testing improved fuel and construction materials. The directions for improving the technical-economic performance characteristics of fast reactors that the BN-800 and -1800 designs can provide are described. It is shown that economic performance indicators which are at least as good as those of VVÉR reactor with close power levels can be achieved.

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Concept of an advanced power-generating unit with a BN-1200 sodium-cooled fast reactor

et al. 2010

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The status of work on the development of a 1200 MW sodium-cooled reactor facility for serial construction is presented. The general characteristics of the facility and the power-generating unit as well as the objectives which must be attained as a result of the design are presented. The design of the power-generating group is based on solutions some of which have been checked during the operation of sodium-cooled reactors in Russia and some have been validated by the appropriate research and development work performed for BN-800. At the same time, new solutions are used which are aimed at improving the technical-economic indicators and increasing the level of safety. Additional R&D work will be needed to validate them.The nuclear future of Russia and most other countries developing nuclear power involves fast reactors and a closed fuel cycle. Thus far only sodium-cooled fast reactors are ready for commercial adoption on a wide scale. In our country, we have more than 50 years of experience in developing and successfully operating such reactors: BR-5 (1959) → BR-10 (1973-2002) → BOR-60 (1969 -in operation) → BN-350 (1973-1998) → BN-600 (1980 -in operation) → BN-800 (under construction). A design of an advanced power-generating unit with a sodium-cooled BN-1200 reactor as the foundation for the initial step in the serial construction of reactors of this type is under development.Target Indicators of Reactor Facility and Power-Generating Unit Design. The development of a power-generating unit must meet the following requirements set for new-generation reactors and nuclear power plants:1) competitiveness with advanced power-generating unit based on reactors of a different type and power-generating units operating on fossil fuel;2) safety increased to a level that makes it unnecessary to take measures to protect the general public outside the borders of the nuclear power plant site for any possible accidents;3) attainment of breeding ratios from 1.2 (stage 1) to 1.3-1.35 (stage 2) using mixed oxide fuel and 1.45 with nitride fuel; 4) reducing the construction time for serially built power-generating units to 48 months; and 5) possibility of introducing a series of reactors in 2-3 years after the startup of the main power-generating unit.

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Untitled

Cited by 13 publications

References 2 publications

Carburization behavior of AISI 316LN austenitic stainless steel – Experimental studies and modeling

Carburization behavior of AISI 316LN austenitic stainless steel – Experimental studies and modeling

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

Concept of an advanced power-generating unit with a BN-1200 sodium-cooled fast reactor

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