56 research outputs found

    International Conference Nuclear Energy for New Europe 2003 Development of Fast Helium Cooled Reactors in Russia

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    ABSTRACT Nuclear energy of the 21 century will be characterized by the use in its structure of fast reactors wherein nuclear fuel breeding is accomplished along with thermal reactors. A combined use of high-temperature gas cooled reactors on thermal (HTGR) and fast (BGR) neutrons may prove to be one of good solutions to the problem of providing fuel for the future nuclear energy. The high helium temperature at the outlet of such reactors allows both electricity generation and using heat for various processes, such as hydrogen production. The paper presents results of the analysis of efforts on development of fast helium cooled reactor concepts previously undertaken in Russia. Advantages of fast helium cooled reactors (BGR) over fast liquid metal cooled reactors are demonstrated. Various BGR concepts are analyzed. One of the concepts consists in attaining the maximum breeding ratio through the use of a modular reactor with a small core containing 239 Pu without breeder material (the plutonium core reactor). In the second concept, an increase in the reactor power while maintaining the fuel breeding parameters is accomplished in a reactor with a multiplutonium core based on placement of several plutonium cores in a certain periodic structure inside a common uranium blanket. In the third concept, the reactor power is increased through an increase of the core volume using plutonium diluted with 238 U (MOX fuel). The possibility of using in BGR a single-circuit scheme of converting heat to electricity with a gas turbine along with the conventional two-circuit scheme in a steam-turbine cycle is demonstrated. Design development efforts performed in Russia allowed designing a BGR-300 pilot fast helium reactor with electric power level of 300 MW. Main parameters of this reactor are presented. A point is made of the promise offered by international cooperation in development and application of high-temperature helium cooled reactor both on thermal (HTGR) and fast (BGR) neutrons for nuclear energy of the 21 century. 102.
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