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Published in: Thermal Engineering 8/2020

01-08-2020 | WATER TREATMENT AND WATER CHEMISTRY

Features of the Water-Chemical Mode of the I Circuit and Problems of Equipment Operation in the Reactor Units of Atomic Icebreakers

Authors: D. S. Urtenov, Yu. B. Vorobyev, V. E. Karnaukhov, A. L. Malysheva, M. E. Panina, M. L. Lukashenko

Published in: Thermal Engineering | Issue 8/2020

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Abstract

Analysis of the experience gained in operating atomic icebreakers, the specifics of operating equipment of the first circuit, and the organization of the water-chemical regime shows the relationship between the high content of gases in the coolant and the problems of ensuring reliable equipment operation. Spatial modeling of vapor-gas bubbles’ mass transfer in the SG-28 steam generator during damping confirmed the possibility of forming a gas cushion in the stagnant zone of the SG. The abrupt increase in the volumetric content of hydrogen during the transition from the liquid to the gas phase of the water coolant explains the anomalous hydrogenation in the area of weld no. 62 on the tubing of the AO SKBK design steam generators. The multiscale, multiphysical approach to conducting calculations was based on the adaptive use of different calculation codes in accordance with the required degree of analysis detail. Four computational models were developed—a common one based on the Relap5 code and three for the CFD code. An offline scheme of combining codes was used. Within its framework, a consistent decomposition of the general problem into computational domains was carried out; appropriate models for them were used, and organization of information exchange between models was based on the initial and boundary conditions. An analysis of the operating conditions and the nature of the mass transfer of vapor-gas bubbles, taking into account the patterns of their fragmentation, confirms the possibility of their entry into the active zone in transient conditions. The presence of oxygen in vapor-gas bubbles dramatically changes the corrosive environment and can cause the nodular corrosion of zirconium shells. To drastically reduce the content of noncondensable gases in the coolant of the first circuit, it was proposed to study the possibility of using a steam volume pressurizer instead of a gas pressurizer in promising projects of transport nuclear power plants (NPPs).

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Literature
1.
go back to reference OST 95.10002-95. Water Quality Standards for the First and Third Circuits of the Reactor Unit of the Vessels of the Department of Maritime Transport of the Russian Federation with KLT-40 Water–Water Reactor (Minatom RF, Moscow, 1995). OST 95.10002-95. Water Quality Standards for the First and Third Circuits of the Reactor Unit of the Vessels of the Department of Maritime Transport of the Russian Federation with KLT-40 Water–Water Reactor (Minatom RF, Moscow, 1995).
2.
go back to reference A. I. Kasperovich, I. V. Bychkov, and V. K. Shiryaev, “Gas displacement and gas evolution in the first circuit of a water–water reactor,” Sov. At. Energy 36, 487–490 (1974).CrossRef A. I. Kasperovich, I. V. Bychkov, and V. K. Shiryaev, “Gas displacement and gas evolution in the first circuit of a water–water reactor,” Sov. At. Energy 36, 487–490 (1974).CrossRef
3.
go back to reference P. Cohen, Water Coolant Technology of Power Reactors (Gordon and Breach, New York, 1969; Atomizdat, Moscow, 1973). P. Cohen, Water Coolant Technology of Power Reactors (Gordon and Breach, New York, 1969; Atomizdat, Moscow, 1973).
4.
go back to reference S. A. Kabakchi, A. V. Luzakov, D. S. Urtenov, E. A. Katanova, I. A. Gasai, and A. E. Verkhovskii, “Evaluation of the corrosion state of equipment of the first circuit of transport nuclear reactors using the parameters of water chemistry,” Therm. Eng. 66, 183–188 (2019). https://doi.org/10.1134/S0040601519030030 CrossRef S. A. Kabakchi, A. V. Luzakov, D. S. Urtenov, E. A. Katanova, I. A. Gasai, and A. E. Verkhovskii, “Evaluation of the corrosion state of equipment of the first circuit of transport nuclear reactors using the parameters of water chemistry,” Therm. Eng. 66, 183–188 (2019). https://​doi.​org/​10.​1134/​S004060151903003​0 CrossRef
5.
go back to reference Yu. A. Kalaida, Yu. D. Katkov, V. A. Kuznetsov, A. Yu. Lastovtsev, A. I. Lastochkin, and V. S. Sysoev, “Solubility of nitrogen in water,” Sov. At. Energy 48, 102–106 (1980).CrossRef Yu. A. Kalaida, Yu. D. Katkov, V. A. Kuznetsov, A. Yu. Lastovtsev, A. I. Lastochkin, and V. S. Sysoev, “Solubility of nitrogen in water,” Sov. At. Energy 48, 102–106 (1980).CrossRef
6.
go back to reference V. P. Baranenko, V. S. Sysoev, V. I. Fal’kovskii, V. S. Kirov, A. I. Piontkovskii, and A. I. Musienko, “The solubility of nitrogen in water,” Sov. At. Energy 68, 162–165 (1990).CrossRef V. P. Baranenko, V. S. Sysoev, V. I. Fal’kovskii, V. S. Kirov, A. I. Piontkovskii, and A. I. Musienko, “The solubility of nitrogen in water,” Sov. At. Energy 68, 162–165 (1990).CrossRef
7.
go back to reference V. S. Sysoev, “On the solubility of the working fluid in the coolant pressurizer system of the primary loop, steam generating units, and water-cooled water-moderated reactor,” Sov. At. Energy 26, 529–531 (1969).CrossRef V. S. Sysoev, “On the solubility of the working fluid in the coolant pressurizer system of the primary loop, steam generating units, and water-cooled water-moderated reactor,” Sov. At. Energy 26, 529–531 (1969).CrossRef
8.
go back to reference P. V. Bychkov and A. I. Kasperovich, “Gas evolution in the first loop of a water-cooled, water-moderated reactor with gas volume compensators,” Sov. At. Energy 28, 180 (1970).CrossRef P. V. Bychkov and A. I. Kasperovich, “Gas evolution in the first loop of a water-cooled, water-moderated reactor with gas volume compensators,” Sov. At. Energy 28, 180 (1970).CrossRef
9.
go back to reference Yu. F. Bodnar’, “Gas evolution in the primary loop of a pressurized-water reactor with gas volume compensators,” Sov. At. Energy 31, 864–866 (1971).CrossRef Yu. F. Bodnar’, “Gas evolution in the primary loop of a pressurized-water reactor with gas volume compensators,” Sov. At. Energy 31, 864–866 (1971).CrossRef
10.
go back to reference RELAP5/MOD3.3. Code Manual, NUREG/CR–5535/, Rev. P3, Vol. 1–5 (U. S. Nuclear Regulatory Commission, Washington, DC, 2003). RELAP5/MOD3.3. Code Manual, NUREG/CR–5535/, Rev. P3, Vol. 1–5 (U. S. Nuclear Regulatory Commission, Washington, DC, 2003).
11.
go back to reference G. P. Kobylyanskii and A. E. Novoselov, Radiation Resistance of Zirconium and Its Alloys. Handbook on Reactor Materials Science, Ed. by V. A. Tsykanov (Nauchno-Issled. Inst. At. Reakt., Dimitrovgrad, 1996) [in Russian]. G. P. Kobylyanskii and A. E. Novoselov, Radiation Resistance of Zirconium and Its Alloys. Handbook on Reactor Materials Science, Ed. by V. A. Tsykanov (Nauchno-Issled. Inst. At. Reakt., Dimitrovgrad, 1996) [in Russian].
12.
go back to reference V. E. Karnaukhov, V. S. Ustinov, D. S. Urtenov, Yu. B. Vorob’ev, Yu. B. Zudin, and M. L. Lukashenko, “Features of mass transfer of noncondensable gases by primary coolant of nuclear icebreaker reactors,” At. Energy (N. Y., NY, U. S.) 127, 77–82 (2019). V. E. Karnaukhov, V. S. Ustinov, D. S. Urtenov, Yu. B. Vorob’ev, Yu. B. Zudin, and M. L. Lukashenko, “Features of mass transfer of noncondensable gases by primary coolant of nuclear icebreaker reactors,” At. Energy (N. Y., NY, U. S.) 127, 77–82 (2019).
13.
go back to reference J. O. Hinze, “Fundamentals of the hydrodynamic mechanism of splitting in dispersion processes,” AIChE J. 1, 289–295 (1955).CrossRef J. O. Hinze, “Fundamentals of the hydrodynamic mechanism of splitting in dispersion processes,” AIChE J. 1, 289–295 (1955).CrossRef
15.
go back to reference R. P. Hesketh, T. W. F. Russell, and A. W. Etchells, “Bubble size in horizontal pipelines,” AIChE J. 33, 663–667 (1987).CrossRef R. P. Hesketh, T. W. F. Russell, and A. W. Etchells, “Bubble size in horizontal pipelines,” AIChE J. 33, 663–667 (1987).CrossRef
19.
go back to reference V. I. Polunichev and A. F. Filimonov, “Possible ways to increase the lifespan of active zones with zirconium-based fuel cells for prospective reactor units of ships and small nuclear power plants,” Tr. NGTU, No. 4 (127), 104–112 (2019). V. I. Polunichev and A. F. Filimonov, “Possible ways to increase the lifespan of active zones with zirconium-based fuel cells for prospective reactor units of ships and small nuclear power plants,” Tr. NGTU, No. 4 (127), 104–112 (2019).
Metadata
Title
Features of the Water-Chemical Mode of the I Circuit and Problems of Equipment Operation in the Reactor Units of Atomic Icebreakers
Authors
D. S. Urtenov
Yu. B. Vorobyev
V. E. Karnaukhov
A. L. Malysheva
M. E. Panina
M. L. Lukashenko
Publication date
01-08-2020
Publisher
Pleiades Publishing
Published in
Thermal Engineering / Issue 8/2020
Print ISSN: 0040-6015
Electronic ISSN: 1555-6301
DOI
https://doi.org/10.1134/S0040601520080078

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