Zobrazeno 1 - 10
of 21
pro vyhledávání: '"C. B. Baxi"'
Autor:
V. F. Golovko, N. G. Kodochigov, I.V. Drumov, S. E. Belov, Arkal Shenoy, A. Telengator, M. N. Borovkov, I. V. Dmitrieva, D.S. Znamensky, C. B. Baxi, J. Razvi
Publikováno v:
Nuclear Engineering and Design. 251:2-17
The special feature of high-temperature gas-cooled reactors (HTGRs) is stressed operating conditions for equipment due to high temperature of the primary circuit helium, up to 950 °C, as well as acoustic and hydrodynamic loads upon the gas path elem
Publikováno v:
Nuclear Engineering and Design. 251:344-348
The gas turbine modular helium reactor (GT-MHR) combines a modular high-temperature gas-cooled reactor (HTGR) nuclear heat source with a closed Brayton gas-turbine cycle power conversion unit (PCU) for thermal to electric energy conversion. The PCU h
Autor:
C. B. Baxi, A. V. Vasyaev, N. G. Kodochigov, S. E. Belov, Arkal Shenoy, V.I. Kostin, V. F. Golovko
Publikováno v:
Nuclear Engineering and Design. 238:2995-3001
General Atomics in the USA and Experimental Design Bureau of Machine Building (OKBM) in the Russian Federation have jointly developed a nuclear power plant design, the gas turbine modular helium reactor (GT-MHR). There have been considerable improvem
Autor:
Hideaki Matsuura, Yasuyuki Nakao, Kazuhiko Kudo, Kenichi Kurihara, Nikolai G. Basov, Nikolai I. Belousov, Peter A. Grishunin, Vladimir V. Kharitonov, Vladislav B. Rozanov, Valery I. Subbotin, M. M. Menon, P. M. Anderson, C. B. Baxi, A. Langhorn, J. L. Luxon, M. A. Mahdavi, Peter K. Mioduszewski, L. W. Owen, M. J. Schaffer, K. M. Schaubel, J. P. Smith, Zaphar-Ullah Koreshi, Asaf Kinrot, Jeffery D. Lewins, Carlos A. Ordonez, Chun-Ching Chien, Theresa Chen Huang, M. K. S. Ray, R. D. Saini, D. Das, G. Chattopadhyay, R. Parthasarathy, S. P. Garg, R. Venkataramani, B. K. Sen, T. S. Iyengar, K. K. Kutty, D. N. Wagh, H. N. Bajpai, C. S. P. Iyer, Kyuichi Yasui
Publikováno v:
Fusion Technology. 22:323-327
Publikováno v:
Journal of Engineering for Gas Turbines and Power. 131
This paper deals with the issue of increasing efficiency of nuclear power plants with the modular high-temperature gas reactor (HTGR) and direct gas-turbine cycle. It should be noted that only this combination can highlight the advantages of the HTGR
Publikováno v:
Volume 4: Cycle Innovations; Industrial and Cogeneration; Manufacturing Materials and Metallurgy; Marine.
The high-temperature gas-cooled reactor technology is the only nuclear technology capable of achieving coolant temperatures as high as 950 °C and at the same time ensuring safe and efficient production of electricity, process steam and hydrogen. GA
Publikováno v:
Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2.
The high-temperature gas-cooled reactor technology is the only nuclear technology capable of achieving coolant temperatures as high as 950 °C and at the same time ensuring safe and efficient production of both electricity and hydrogen. OKBM and GA s
Autor:
C. B. Baxi
Publikováno v:
Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 1.
Due to problems with the availability and the price of water, and the concerns relating to adverse environmental effects of wet cooling systems, the need for water conserving cooling systems has been increasing. Presently, dry cooling accounts for ov
Publikováno v:
Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2.
A power-generating unit with the high-temperature helium reactor (GT-MHR) has a turbomachine (TM) that is intended for both conversion of coolant thermal energy into electric power in the direct gas-turbine cycle, and provision of helium circulation
Publikováno v:
Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 1.
The paper deals with the issue of increasing efficiency of nuclear power plants with the modular high-temperature helium reactor (HTGR) and direct gas turbine cycle. It should be noted that only this combination can highlight the advantages of the HT