Abstract
In the case of using high-temperature sodium-cooled nuclear power installations for obtaining hydrogen and for other innovative applications (gasification and fluidization of coal, deep petroleum refining, conversion of biomass into liquid fuel, in the chemical industry, metallurgy, food industry, etc.), the sources of hydrogen that enters from the reactor plant tertiary coolant circuit into its secondary coolant circuit have intensity two or three orders of magnitude higher than that of hydrogen sources at a nuclear power plant (NPP) equipped with a BN-600 reactor. Fundamentally new process solutions are proposed for such conditions. The main prerequisite for implementing them is that the hydrogen concentration in sodium coolant is a factor of 100–1000 higher than it is in modern NPPs taken in combination with removal of hydrogen from sodium by subjecting it to vacuum through membranes made of vanadium or niobium. Numerical investigations carried out using a diffusion model showed that, by varying such parameters as fuel rod cladding material, its thickness, and time of operation in developing the fuel rods for high-temperature nuclear power installations (HT NPIs) it is possible to exclude ingress of cesium into sodium through the sealed fuel rod cladding. However, if the fuel rod cladding loses its tightness, operation of the HT NPI with cesium in the sodium will be unavoidable. Under such conditions, measures must be taken for deeply purifying sodium from cesium in order to minimize the diffusion of cesium into the structural materials.
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References
E. E. Shpil’rain, S. P. Malyshenko, and G. G. Kuleshov, An Introduction to Hydrogen Power Engineering, Ed. by V. A. Legasov (Energoatomizdat, Moscow, 1984) [in Russian].
V. I. Rachkov, “Nuclear power engineering as a factor of utmost importance for sustainable development of Russia in the 21st century,” Energosber. Vodopodg., No. 6, 2–4 (2006).
E. O. Adamov, A. V. Dzhalavyan, A. V. Lopatkin, N. A. Molokanov, E. V. Murav’ev, V. V. Orlov, S. G. Kalyakin, V. I. Rachkov, V. M. Troyanov, E. N. Avrorin, V. B. Ivanov, and R. M. Aleksakhin, “The conceptual statements in the strategy for development of the Russian nuclear power industry in the out-look up to 2100,” At. Energ. 112(6), 319–330 (2012).
V. I. Rachkov, V. M. Poplavskii, A. M. Tsibulya, Yu. E. Bagdasarov, B. A. Vasil’ev, Yu. L. Kamanin, S. L. Osipov, N. G. Kuzavkov, V. N. Ershov and M. R. Ashirmetov, “The concept of a prospective power unit equipped with a BN-1200 fast-neutron sodium-cooled reactor,” At. Energ. 108(4), 201–205 (2010).
V. V. Alekseev, Yu. P. Kovalev, S. G. Kalyakin, F. A. Kozlov, V. Ya. Kumaev, A. S. Kondrat’ev, V.V. Matyukhin, E. P. Pirogov, G. P. Sergeev, A. P. Sorokin, and I. Yu. Torbenkova, “Sodium coolant purification systems for a nuclear power station equipped with a BN-1200 reactor,” Therm. Eng. 60(5), 311 (2013), DOI: 10.1134/S0040363613050019.
V. M. Poplavskii, A. N. Zabud’ko, E. E. Petrov, M. K. Ovcharenko, V. V. Popov, V. B. Bogush, N. I. Loginov, V. A. Tarasov, V. B. Polevoi, V. A. Khoromskii, and A. S. Mikheev, “Physical characteristics and problems associated with development of a sodium-cooled fast-neutron reactor as a source of high-grade thermal energy for producing hydrogen and for use in other high-temperature technologies,” At. Energ. 106(3), 129–134 (2009).
F. A. Kozlov, L. G. Volchkov, E. K. Kuznetsov, and V. V. Matyukhin, Liquid-Metal Coolants of Nuclear Power Installations: Purification from Impurities and Their Monitoring, Ed. by F. A. Kozlov (Energoatomizdat, Moscow, 1983) [in Russian].
A. C. Wittingam, “An equilibrium and kinetic study of the liquid sodium-hydrogen reaction and its relevance to sodium-water leak detection in LMFBR systems,” J. Nucl. Mater. 60, 119–131 (1976).
A. V. Morozov and A. P. Sorokin, “Methods for obtaining hydrogen and prospects of using a high-temperature sodium-cooled fast-neutron reactor for its production,” in Proceedings of the International Seminar “High-Temperature Projects,” Kalpakkam, India, November 14–15, 2011.
N. L. Plate and E. V. Slivinskii, Chemical Principles of Monomer Technology: A Handbook (IAPC Nauka/Interperiodika, Moscow, 2002) [in Russian].
Yu. V. Chechetkin, V. D. Kizin, and V. I. Polyakov, Radiation Safety of an NPP Equipped with a Sodium-Cooled Fast-Neutron Reactor (Energoatomizdat, Moscow, 1983) [in Russian].
D. A. Karpov, I. F. Kislov, S. N. Mazaev, V. Ya. Moiseev, A. P. Shabanov, G. V. Dubinin, V. A. Dubrovskii, and I. A. Khazov, “Studying the possibility of using protective coatings for reducing hydrogen penetration through the structural materials,” URL: http://www.rvs.itsoft.ru:8000/article/sart.html?id=239&conf-id=4.
F. A. Kozlov and L. G. Volchkov, “A method for regenerating the cold traps of impurities in alkali metals,” USSR Inventor’s Certificate No. 429468, Byul. Otkr., Izobr., No. 19 (1974).
F. A. Kozlov and L. G. Volchkov, “A new method for regenerating the traps for purifying alkali metal coolants,” At. Energ. 39(4), 310 (1975).
F. A. Kozlov, L. G. Volchkov, B. I. Tonov, Yu. P. Nali- mov, and V. A. Likharev, “A method for regenerating the cold traps of impurities in alkali metal coolants,” USSR Inventor’s Certificate No. 473221, Byul. Otkr., Izobr., No. 21 (1975).
G. Eshbakh, U. Gross, K. Llayapcoeprep, and S. Shullien, “Hydrogen diffusion and penetration through steel,” in Sorption Processes in Vacuum, Ed. by K. N. Myznikov (Atomizdat, Moscow, 1966) [in Russian].
J.-L. Courouau and D. Labatut, “Hydrogen and tritium distribution in FBRs. Modelling and cross-over calculations in a reference case for the PHENIX and BN-600 reactors,” Note Technique, No. 97036 dated 25.06.97 (Cadarache, 1997), pp. 17–20.
L. F. Belovodskii, V. K. Gaevoi, and V. I. Grishmanovskii, Tritium (Energoatomizdat, Moscow, 1985) [in Russian].
E. Fromm and E. Gebkhart, Gases and Carbon in Metals (Metallurgiya, Moscow, 1980) [in Russian].
A. I. Lastov, E. A. Pavlinchuk, E. U. Konovalov, I. G. Sheinker, L. F. Lastova, I. A. Efimov, and A. N. Mezentsev, “Distribution of radionuclides over the primary circuit pipeline wall thickness in a BR-10 reactor,” At. Energ. 60(4), 262–264 (1986).
F. A. Kozlov and M. A. Konovalov, “Assessment of cesium release through the steel claddings in a high-temperature sodium coolant,” in Proceedings of the Scientific-Technical Conference “Thermal Physics-2012,” GNTs RF-FEI, Obninsk, 2012, pp. 115–116.
H. J. Matzke and G. Linker, “Study of the diffusion of cesium in stainless steel using ion beams,” J. Nucl. Mater. 64(1–2), 130–138 (1977).
V. I. Isaichev, L. N. Larikov, and L. F. Chernaya, “About the diffusion mechanism of group IV elements in Mo and W,” Ukr. Fiz. Zh. 25(4), 591–598 (1980).
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Original Russian Text © F.A. Kozlov, A.P. Sorokin, V.V. Alekseev, M.A. Konovalov, 2014, published in Teploenergetika.
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Kozlov, F.A., Sorokin, A.P., Alekseev, V.V. et al. The high-temperature sodium coolant technology in nuclear power installations for hydrogen power engineering. Therm. Eng. 61, 348–356 (2014). https://doi.org/10.1134/S004060151405005X
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DOI: https://doi.org/10.1134/S004060151405005X