The Experts below are selected from a list of 276 Experts worldwide ranked by ideXlab platform

R.j. Patel - One of the best experts on this subject based on the ideXlab platform.

  • High temperature reactor technology development in India
    Progress in Nuclear Energy, 2017
    Co-Authors: I.v. Dulera, R. K. Sinha, A. Rama Rao, R.j. Patel
    Abstract:

    Abstract High Temperature Reactor technology development programme was initiated in India with an aim to provide high temperature process heat for nuclear hydrogen production by splitting water. As high efficiency hydrogen production needs process heat at temperatures around 1123 K, a challenging technology development goal for the high temperature reactors was set to achieve Coolant temperature of 1273 K. Currently development is in progress for a Compact High Temperature Reactor (CHTR), and a 600 MWth Innovative High Temperature Reactor (IHTR). Current design version of CHTR has 235U based TRISO (TRistructural-ISOtropic) coated particle fuel, Beryllium oxide (BeO) as moderator, graphite as reflector, and lead-bismuth eutectic (LBE) as the Coolant. The design incorporates many passive safety features for reactor heat removal. Current design version of IHTR is based on pebble bed fuel configuration with molten salt as Coolant. For both the reactors, reactor heat is removed passively by natural circulation of the Coolant. Technology development for these reactors include development of TRISO coated particle fuel, lead-bismuth eutectic and molten salt Coolant technologies, BeO and graphite, oxidation resistant coatings, high creep strength alloys compatible to these Coolants, high temperature instrumentation for these Coolants, as well as high efficiency hydrogen production and electricity generation technologies.

I.v. Dulera - One of the best experts on this subject based on the ideXlab platform.

  • High temperature reactor technology development in India
    Progress in Nuclear Energy, 2017
    Co-Authors: I.v. Dulera, R. K. Sinha, A. Rama Rao, R.j. Patel
    Abstract:

    Abstract High Temperature Reactor technology development programme was initiated in India with an aim to provide high temperature process heat for nuclear hydrogen production by splitting water. As high efficiency hydrogen production needs process heat at temperatures around 1123 K, a challenging technology development goal for the high temperature reactors was set to achieve Coolant temperature of 1273 K. Currently development is in progress for a Compact High Temperature Reactor (CHTR), and a 600 MWth Innovative High Temperature Reactor (IHTR). Current design version of CHTR has 235U based TRISO (TRistructural-ISOtropic) coated particle fuel, Beryllium oxide (BeO) as moderator, graphite as reflector, and lead-bismuth eutectic (LBE) as the Coolant. The design incorporates many passive safety features for reactor heat removal. Current design version of IHTR is based on pebble bed fuel configuration with molten salt as Coolant. For both the reactors, reactor heat is removed passively by natural circulation of the Coolant. Technology development for these reactors include development of TRISO coated particle fuel, lead-bismuth eutectic and molten salt Coolant technologies, BeO and graphite, oxidation resistant coatings, high creep strength alloys compatible to these Coolants, high temperature instrumentation for these Coolants, as well as high efficiency hydrogen production and electricity generation technologies.

R. K. Sinha - One of the best experts on this subject based on the ideXlab platform.

  • High temperature reactor technology development in India
    Progress in Nuclear Energy, 2017
    Co-Authors: I.v. Dulera, R. K. Sinha, A. Rama Rao, R.j. Patel
    Abstract:

    Abstract High Temperature Reactor technology development programme was initiated in India with an aim to provide high temperature process heat for nuclear hydrogen production by splitting water. As high efficiency hydrogen production needs process heat at temperatures around 1123 K, a challenging technology development goal for the high temperature reactors was set to achieve Coolant temperature of 1273 K. Currently development is in progress for a Compact High Temperature Reactor (CHTR), and a 600 MWth Innovative High Temperature Reactor (IHTR). Current design version of CHTR has 235U based TRISO (TRistructural-ISOtropic) coated particle fuel, Beryllium oxide (BeO) as moderator, graphite as reflector, and lead-bismuth eutectic (LBE) as the Coolant. The design incorporates many passive safety features for reactor heat removal. Current design version of IHTR is based on pebble bed fuel configuration with molten salt as Coolant. For both the reactors, reactor heat is removed passively by natural circulation of the Coolant. Technology development for these reactors include development of TRISO coated particle fuel, lead-bismuth eutectic and molten salt Coolant technologies, BeO and graphite, oxidation resistant coatings, high creep strength alloys compatible to these Coolants, high temperature instrumentation for these Coolants, as well as high efficiency hydrogen production and electricity generation technologies.

A. Rama Rao - One of the best experts on this subject based on the ideXlab platform.

  • High temperature reactor technology development in India
    Progress in Nuclear Energy, 2017
    Co-Authors: I.v. Dulera, R. K. Sinha, A. Rama Rao, R.j. Patel
    Abstract:

    Abstract High Temperature Reactor technology development programme was initiated in India with an aim to provide high temperature process heat for nuclear hydrogen production by splitting water. As high efficiency hydrogen production needs process heat at temperatures around 1123 K, a challenging technology development goal for the high temperature reactors was set to achieve Coolant temperature of 1273 K. Currently development is in progress for a Compact High Temperature Reactor (CHTR), and a 600 MWth Innovative High Temperature Reactor (IHTR). Current design version of CHTR has 235U based TRISO (TRistructural-ISOtropic) coated particle fuel, Beryllium oxide (BeO) as moderator, graphite as reflector, and lead-bismuth eutectic (LBE) as the Coolant. The design incorporates many passive safety features for reactor heat removal. Current design version of IHTR is based on pebble bed fuel configuration with molten salt as Coolant. For both the reactors, reactor heat is removed passively by natural circulation of the Coolant. Technology development for these reactors include development of TRISO coated particle fuel, lead-bismuth eutectic and molten salt Coolant technologies, BeO and graphite, oxidation resistant coatings, high creep strength alloys compatible to these Coolants, high temperature instrumentation for these Coolants, as well as high efficiency hydrogen production and electricity generation technologies.

A. P. Sorokin - One of the best experts on this subject based on the ideXlab platform.

  • Use of liquid metals in nuclear and thermonuclear engineering, and in other innovative technologies
    Thermal Engineering, 2014
    Co-Authors: V. I. Rachkov, A. D. Efanov, F. A. Kozlov, M. N. Arnol’dov, S. G. Kalyakin, N. I. Loginov, Yu. I. Orlov, A. P. Sorokin
    Abstract:

    By now, a good deal of experience has been gained with using liquid metals as Coolants in nuclear power installations; extensive knowledge has been gained about the physical, thermophysical, and physicochemical properties of these Coolants; and the scientific principles and a set of methods and means for handling liquid metals as Coolants for nuclear power installations have been elaborated. Prototype and commercialgrade sodium-cooled NPP power units have been developed, including the BOR-60, BN-350, and BN-600 power units (the Soviet Union); the Rapsodie, Phenix, and Superphenix power units (France), the EBR-II power unit (the United States); and the PFR power unit (the United Kingdom). In Russia, dedicated nuclear power installations have been constructed, including those with a lead-bismuth Coolant for nuclear submarines and with sodium-potassium alloy for spacecraft (the Buk and Topol installations), which have no analogs around the world. Liquid metals (primarily lithium and its alloy with lead) hold promise for use in thermonuclear power engineering, where they can serve not only as a Coolant, but also as tritium-producing medium. In this article, the physicochemical properties of liquid metal Coolants, as well as practical experience gained from using them in nuclear and thermonuclear power engineering and in innovative technologies are considered, and the lines of further research works are formulated. New results obtained from investigations carried out on the Pb-Bi and Pb for the SVBR and BREST fast-neutron reactors (referred to henceforth as fast reactors) and for controlled accelerator systems are described.

  • Sodium as a Coolant for fast reactors
    Atomic Energy, 2010
    Co-Authors: V. M. Poplavskii, A. D. Efanov, F. A. Kozlov, A. P. Sorokin, A. S. Korol'kov, Yu. E. Shtynda
    Abstract:

    The results of a comparative analysis and choice of sodium as the Coolant for fast reactors are presented. The facilities developed for removing impurities present in the sodium Coolant and monitoring their content are described. The modeling of the mass transfer of impurities in Coolants and the development of new liquid-metal Coolants are examined. The results of an analysis of the anomalous situations in fast reactors, and methods for removing Coolant residues from equipment and salvaging wastes are presented. It is shown that the technical solutions adopted provide reliable protection from accidents. New problems of sodium technology are formulated in application to the development of a new generation of fast reactors.