共 40 条
[1]
Samoilov O.B., Kurachenkov A.V., Nuclear district heating plants AST-500. Present status and prospects for future in Russia, Nuclear Engineering and Design, 173, 1-3, pp. 109-117, (1997)
[2]
Delmastro D.F., Thermal-hydraulic aspects of CAREM reactor, Proceeding of the IAEA Technical Committee Meeting on Natural Circulation Data and Innovative Nuclear Power Plant Design
[3]
Sinha R.K., Kakodkar A., Requirements for the design of advanced heavy water reactor, Proceedings of IAEA TCM Workshop on Requirements for the Next Generation of Water Cooled Reactor
[4]
Kuznetsov Y.N., Romenkov A.A., Alekseev A.I., Lisitsa F.D., Tokarev Y.I., Yarmolenko O.A., NPP with VK-300 boiling water reactor for power and district heating grids, Proceedings of International Seminar on Small and Medium Sized Reactors: Status and Prospects, Organized by IAEA
[5]
Silin V.A., Voznesensky V.A., Afrov A.M., The light water integral reactor with natural circulation of the coolant at supercritical pressure B-500 SKDI, Nuclear Engineering and Design, 144, 2, pp. 327-336, (1993)
[6]
Bushby S.J., Dimmick G.R., Duffey R.B., Spinks N.J., Burrill K.A., Chan P.S.W., Conceptual designs for advanced, high-temperature CANDU reactors, Proceedings of the Supercritical Water Reactors Symposium (SCR-2000)
[7]
Zvirin Y., A review of natural circulation loops in pressurised water reactors and other systems, Nuclear Engineering and Design, 67, 2, pp. 203-225, (1981)
[8]
Greif R., Natural circulation loops, Journal of Heat Transfer, 110, pp. 1243-1258, (1988)
[9]
Yadigaroglu G., Delhaye J.M., Giot M., Reithmuller M.L., Two-phase flow instabilities and propagation phenomena, Thermohydraulics of Two-Phase Systems for Industrial Design and Nuclear Engineering, (1978)
[10]
Kakac S., Review of two-phase flow instabilities, Journal of Pure and Applied Sciences, 18, pp. 171-252, (1985)