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Fast Reactors in Russia: State of the Art and Trends of Development

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Fast Reactors in Russia: State of the Art and Trends of Development XA0202595 Annex XIII: Russia FAST REACTORS IN RUSSIA: STATE OF THE ART AND TRENDS OF DEVELOPMENT V. M. Popiavsky1), Yu. M. Ashurko1>, K. V. Zverev 2), N. N. Oshkanov 3), A. S. Koroi'kov 4), A. i. Filin 5) 1) State Scientific Center of the Russian Federation - Institute for Physics and Power Engineering (SSC RF IPPE), Obninsk; 2) Ministry of the Russian Federation for Atomic Energy (RF MiNATOM), Moscow; o) Beloyarskaya Nuclear Power Plant (BN PP), Zarechny, 4) State Scientific Center of the Russian Federation - Research institute of Atomic Reactors (SSC RF- RIAR), Dimitrovgrad; 5) Research and Design institute of Power Engineering (RDIPE), Moscow Submitted to 35th Meeting of IAEA Technical Working Group on Fast Reactors, Karlsruhe, Germany, 22-26 April 2002 CONTENTS 1. NUCLEAR POWER IN RUSSIA 1.1. NUCLEAR POWER OF RUSSIA IN 2001-2002 1.2. PLANS OF FURTHER DEVELOPMENT OF NUCLEAR POWER IN RUSSIA 2. FAST REACTORS 2.1. FAST REACTOR OPERATION IN 2001 2.1.1. BN-600 REACTOR NPP 2.1.2. EXPERIMENTAL REACTOR BOR-60 2.1.3. EXPERIMENTAL REACTOR BR-10 2.2. CONSTRUCTION OF NPP WITH BN-800 REACTOR 2.3. PARTICIPATION IN WORK ON BN-350 REACTOR DECOMMISSIONING 2.4. MAIN TRENDS OF DESIGN STUDIES IN FAST REACTOR AREA 3. ACCELERATOR DRIVEN SYSTEMS 1. NUCLEAR POWER IN RUSSIA 1.1. NUCLEAR POWER OF RUSSIA IN 2001 - 2002 In Table 1 presented are the number and types of NPP units operated in Russia. The first power unit of Rostovskaya NPP with WER-1000 reactor joined this number last year: it was started up on February 23, 2001 and put into commercial operation at the end of the year. Total power of 30 reactor units installed at 10 NPP is now equal to 22.242 GW sharing as much as 15% of total energy production in Russia. In the European Russia, this share is 20 % in average, reaching 30 to 40% in the industrial areas (north-western and central regions of European territory of Russia). In 2001, 134948.1 million kW-h of electric energy was produced by the NPP, i.e. -104.7 % of 2000 year's production. During the previous two years, about 50 % of total energy production increase in Russia has been provided by the nuclear power plants. In 2001, average load factor value for all NPPs (except for the first power unit of Rostovskaya NPP, which was on semi-commercial operation stage) was equal to 70.26 % as compared to 69.07 % in 2000. Scheduled reactor outage time was also taken into account thus decreasing load factor value. During 2001, 66 cases of abnormal reactor operation took place in the NPP including 46 cases referring to "0" level of INES and 20 "out of scale" cases. Figs. 1 and 2 show dynamics of NPP abnormal operation cases for the previous nine years, including those are related to safety according to the INES. 1.2. PLANS OF FURTHER DEVELOPMENT OF NUCLEAR POWER IN RUSSIA Federal policy of Russia in the area of nuclear power is determined by the "Power industry Strategy of Russia Until 2020" and related "Strategy of Nuclear Power Development in Russia in the First Half of XXI Century". The following two power units are planned for putting into operation until 2005: - fifth power unit of Kurskaya NPP with RBMK-1000 reactor; - third power unit of Kalininskaya NPP with WER-1000 reactor. Work is now under way on lifetime extension by 10 years for the power units in operation, and primarily for the first generation power units. In the period until 2010, 9 new power units of 8.8 GW totai output are planned to put into operation in the Russian Federation, including that with the BN-800 reactor in Beloyarskaya NPP. In the next decade (2010-2020), it is planned to increase the rate of introduction of nuclear power by 2 to 2.5 times, i.e. up to 2.5 million kW per year. The rate of increase of electricity production at NPP will be about 5% per year until 2020, being twice as much as that for fossil fuel and hydro-electric power plants. Nuclear power share in the European Russia will increase from 20% (as of 2000) up to 27% by 2010 and 37% by 2020. This means that structural change is planned in the national power industry in favor of nuclear power. boo Table 1 List of operating nuclear power units in Russia Year of putting Installed electric No. NPP No. of Reactor type >ower uni into operation power, MW 1 1 „., 1973 440 ! 2 2 WER-440 1974 440 WER-440 I 3 3 1981 440 Kola NPP WER-440 | 4— 4 1984 440 WER-440 NPP 1760 3 WER-440 1971 417 Novovoronezh NPP 4 WER-440 1972 417 TOTAL FOR WER-440 2594 7 5 WER-1000 1980 1000 Novovoronezh NPP NPP 1834 8 1 WER-1000 1985 1000 9 2 WER-1000 1987 1000 I 10 Baiakovo NPP 3 WER-1000 1988 1000 ! 11 4 WER-1000 1993 1000 : I NPP I 4000 ! 12 1 WER-1000 1984 1000 I 13 Kalinin NPP 2 WER-1000 1986 1000 NPP 2000 i 14 Rostov NPP -j WER-1000 2001 1000 TOTAL FOR WER-1000 8000 ! 15 1 RBMK-1000 1976 1000 ! 16 RBMK-1000 1979 1000 17 Kursk NPP RBMK-1000 1983 1000 18 A RBMK-1000 1985 1000 j NPP 4000 i 19 RBMK-1000 1973 1000 20 RBMK-1000 1975 1000 21 Leningrad NPP 3 RBMK-1000 1979 1000 j 22 4 RBMK-1000 1981 1000 I NPP 4000 23 RBMK-1000 1982 1000 24 RBMK-1000 1985 1000 Smolensk NPP ; 25 RBMK-1000 1990 1000 I NPP 3000 TOTAL FOR RBMK •:•'" : . : 11000 26 EGP-6 1974 12 27 2 EGP-6 1974 A O 28 Bilibino NPP EGP-6 1975 12 29 EGP-6 1976 12 NPP 48 | 30 Beloyarskaya NPP <BN) i L BN-600 1980 600 TOTAL NUCLEAR POWER 22242 564 2. FAST REACTORS 2.1. FAST REACTOR OPERATION IN 2001 During 2001, three fast reactors were in operation in Russia: - experimental reactor BR-10 (IPPE, Obninsk); - experimental reactor BOR -60 (RIAR, Dimitrovgrad); - NPP with BN-600 reactor (BNPP, Zarechny). 2.1.1. BN-600 REACTOR NPP As of 28 January 2002, total time of the BN-600 reactor operation under critical condition since its first start-up is 150000 hours (which is equal to 17.1 years), including 15.4 years of operation at the rated power level (5611 eff. days). Average load factor values taken for the whole period of reactor operation and period of its commercial operation are respectively equal to 69.9% and 73.3%. The diagram showing load factor behavior during the period of commercial operation of the BN-600 power unit (upon reaching rated power level of the reactor) is shown in Fig. 3. Fig. 4 presents power unit load carried in 2001. The main characteristics of the BN-600 reactor operation in 2001 and during the whole period since its putting into service are given in Table 2. Table 2 Since start-up to Characteristics 2001 31.12.2001 Energy production, million kW-h 4199.2 79872.9 Heat supply of consumers, thousand Gcaf 376.9 i 4112.4 Load factor, % 79.89 ! 69.9 Time of critical reactor operation, h 7366 I 149348 Number of reactor shut-downs 2 | 89 Number of loop outages 1 | 69 As seen from the load chart (Fig. 4) and Table 2, in 2001 there were two reactor shut-downs for scheduled preventive repair and one loop outage due to loss of excitation of the turbo-generator. No unscheduled reactor shut-downs occurred in this period. Load factor decrease was as follows: - scheduled repair- 18.28%; - external conditions (heat supply) - 0.81 %; - failures of components - 0.37%; - loop outage - 0.65%. Maximum decrease of electric power caused by heat supply by the steam taken from the turbine non-controlled bleed-off and from steam generators in the winter time is 47 MW (~7.8% No). Annual decrease of load factor for this reason is 0.8-5-1.8%. Dates of scheduled preventive repair performed in 2001 are as follows: - medium repair: from 04.05.2001 to 23.06.2001, 50.7 days (Fig. 4, item 2); - routine repair: from 14.10.2001 to 26.10.2001, 13.7 days (Fig. 4, item 4). Loop No. 5 outage lasted from 30.01.2001 to 04.02.2001 (Fig. 4, item 1). Medium and routine repair of the power unit included the following activities: - reactor refueling; - replacement of 8 control rod guide tubes (lifetime expiry); - replacement of 2 safety rod drives (iifetime expiry); - replacement of shafts of No. 4 main pumps of the primary and secondary circuits (iifetime expiry); - elimination of vibration in No.6 main secondary pump and hydraulic drive of the check valve of No. 4 primary pump; - examination of sodium-sodium intermediate heat exchanger 6 1HX-B; - repair of steam pipeline joints at No. 5 steam generator (metal body defect); - examination of steam generator evaporators inciuding cutting out tubes from 5E-A3 evaporator with maximum operating time; - chemical washing of evaporators of SG-6 steam generator; - routine control of metal according to the schedule; - replacement of membranes on 5UPM-C and D safety systems preventing from water leak into sodium (lifetime expiry); - pressurization tests of No. 6 secondary loop; - medium repair of No. 4 turbine implying overhaul of low pressure cylinder; - replacement of No. 4-C feed water pump (lifetime expiry). During 2001, there were no violations of safe operation conditions preset by reactor design even in case of loop outage, which was classified referring to INES as "out of scale" incident.
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