This is a survey of several designs for nuclear power reactors cooled by water at supercritical pressure. Structural solutions for justifying the choice of a preferred variant are examined.
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P. L. Kirillov, “Water cooled reactors with supercritical water parameters (proposals for a program and development paths),” in: Water-Water Supercritical Pressure Power Reactors (VVÉRSKD): A Collection of Papers and Other Materials [in Russian], (2006), URL: http://bookfi.org (checked on December 12, 2012).
V. A. Silin, “What is to be preferred…,” REA, No. 9 (2009).
S. A. Skvortsov and S. M. Feinberg, Use of Supercritical Steam Parameters in Water-Water Power Reactors [in Russian], Preprint, Kurchatov Institute (1961).
V. A. Silin, Yu. M. Semchenkov, P. N. Alekseev, and V. V. Mit’- kin, “Study of heat exchange and hydraulic resistance for water flows with supercritical parameters as applied to reactor systems,” Atom. Énerg., 108(6) (2010).
B. B. Dyadyakin and A. S. Popov, “Heat transfer and hydraulic resistance of a seven-rod bundle cooled by a water flow with supercritical parameters of state,” Trudy VTI, No. 11 (1977).
V. A. Mokhov and M. P. Nikitenko, “Further development of the VVÉR technology,” REA, No. 7 (1911).
Yu. D. Baranaev, A. P. Glebov, A. V. Klushin, V. Ya. Kozlov, V. M. Makhin, S. N. Kobelev, S. V. Semiglazov, and V. V. V’yalitsin (eds.), “Reactors cooled by water at supercritical pressure for a two-pass active scheme for coolant flow,” in: Water-Water Supercritical Pressure Power Reactors (VVÉR-SKD ): A Collection of Papers and Other Materials [in Russian], (2006).
P. N. Alekseev and A. A. Sedov, “If there is interest, there will be results,” REA, No. 9 (2009).
V. K. Vikulov, V. E. Gmyrko, I. I. Grozdov, A. A. Petrov, and A. F. Finyakin, “Water-graphite power reactor with supercritical coolant pressure VGÉRS,” in: Water-Water Supercritical Pressure Power Reactors (VVÉR-SKD ): A Collection of Papers and Other Materials [in Russian], (2006).
J. Buongiorno and Ph. E. MacDonald, Supercritical Water Reactor (SCWR ). Progress Report for the FY-03 Generation-IV R&D Activities for the Development of the SCWR in the US, Tech. Report INEEL_EXT-03-01210.
O. M. Galushko, Nuclear Power Plant Equipment. A Textbook for Student “Machine Operator” Professionals and Specialty 151001 “Machine Building Technology” [in Russian], Volgodonsk (2009).
O. Glinskikh, New Generation Nuclear Plants. The Enhanced Safety Power Reactor VPBÉR-600, Talk at 1st Int. Nuclear Conf. “Youth, Future, and Nuclear,” Bratislava, Slovakia, April 2000.
Status of Small and Medium Sized Reactor Designs. A Supplement to the IAEA Advanced Reactors Information System, IAEA Report, September 2012.
I. N. Vasil’chenko, et al., “Design and structural work on the cores of VVÉR reactors with spectrum control,” in: Provision of Safety in Nuclear Power Plants with VVÉR Reactors: Abstrs. of the 7th Int. Sci.-Tech. Conf., Podolsk, Russia, May 17 – 20, 2011 [in Russian], Izd. JSC OKB “Gidropress,” Podolsk (2011).
Y. Oka, Y. Ishiwatari, and S. Koshizuka, “Research and development of super LWR and super fast reactor,” in: Proc. 3rd Int. Symp. on Supercritical Water-Cooled Reactors (SCWR) — Design and Technology, Shanghai, China, March 12 – 15, 2007.
A. P. Ornatskii, Yu. G. Dashkov, and V. G. Perkov, Supercritical Pressure Steam Generators [in Russian], Vishcha Shkola, Kiev (1980).
N. M. Galin and P. L. Kirillov, Heat Transfer (in Nuclear Power Plants ), Énergoatomizdat, Moscow (1987).
P. Dumaz and O. Antoni, “The extension of the CATHARE-2 computer code above the critical point applications to a supercritical light water reactor,” in: Proc. 10 th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics NURETH-10, Seoul, Korea, October 5 – 9, 2003.
V. A. Silin, et al., “Problems with the transition to supercritical water pressure in nuclear power engineering and possible ways of overcoming them,” in: Provision of Safety in Nuclear Power Plants with VVÉR reactors: Abstrs. of the 8th Int. Sci.-Tech. Conf., Podolsk, Russia, May 28 – 31, 2013 [in Russian], Izd. JSC OKB “Gidropress,” Podolsk (2013).
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Translated from Élektricheskie Stantsii, No. 4, April 2014, pp. 11 – 21.
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Silin, V.A., Zorin, V.M. & Khlopov, R.A. Reactors Cooled by Water at Supercritical Pressure. Power Technol Eng 48, 222–231 (2014). https://doi.org/10.1007/s10749-014-0512-z
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DOI: https://doi.org/10.1007/s10749-014-0512-z