An approach to standardizing the water chemistry of the secondary coolant circuit of a nuclear power station with VVER-1000 reactors

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All-Russia Institute for Nuclear, Power Plant Research, Moscow, Russia ^{[1
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Gongcheng Kancha | / 6卷 / 931期

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[41] Assessment of accident management measures on early in-vessel station blackout sequence at VVER-1000 pressurized water reactors
Tusheva, P., 1600, Elsevier Ltd (277):
[42] Equivalent thermal conductivity of the storage basket with spent nuclear fuel of VVER-1000 reactors
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[43] CONTROLLING OUTPUT OF TURBINE-DRIVEN FEEDPUMPS FOR A VVER-1000 REACTOR UNIT OF A NUCLEAR-POWER STATION
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[44] ACTIVITY OF RADIONUCLIDES IN THE COOLANT OF THE SECONDARY LOOP OF A NUCLEAR-POWER PLANT WITH VVER-440 REACTORS
VORONIN, LM
VOLKOV, AP
KOZLOV, VF
LUZANOVA, LM
PASHEVICH, VI
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[45] INVESTIGATING THE STEAM GENERATORS OF THE MAIN UNIT ON A NUCLEAR POWER STATION (AES) WITH A WATER-MODERATED WATER-COOLED VVER-1000 REACTOR.
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[46] EFFECT OF HIGH-TEMPERATURE FILTRATION ON THE COMPOSITION OF COOLANT IMPURITIES IN THE PRIMARY LOOPS OF POWER-GENERATING UNITS WITH VVER-1000 REACTORS
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[47] Experience gained in developing the informational and computational system of a serial power unit of a nuclear power station equipped with a VVER-1000 reactor
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[48] Investigation of Criticality and Relative Power Density Distribution in VVER-1000 Nuclear Power Reactor
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[49] ANALYZING HIGH-TEMPERATURE MECHANICAL FILTER PERFORMANCE AT EXISTING NUCLEAR-POWER STATIONS WITH VVER-1000 REACTORS
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[50] Primary Circuit Coolant Pressure and Quantity Control of a Nuclear Power Station with VVER-440 Reactor.
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