ACTIVITY OF RADIONUCLIDES IN THE COOLANT OF THE SECONDARY LOOP OF A NUCLEAR-POWER PLANT WITH VVER-440 REACTORS

被引：0
|
作者：
VORONIN, LM
VOLKOV, AP
KOZLOV, VF
LUZANOVA, LM
PASHEVICH, VI
机构：
来源：
SOVIET ATOMIC ENERGY | 1979年 / 46卷 / 01期
关键词：
D O I：
10.1007/BF01119948
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
引用
收藏
页码：31 / 35
页数：5
相关论文
共 50 条
  • [21] Effect of the steam generator on temperature fluctuations of the primary circuit coolant in VVER-440 reactors
    Kiss, Sandor
    Lipcsei, Sandor
    ANNALS OF NUCLEAR ENERGY, 2014, 72 : 166 - 172
  • [22] ALGORITHMS AND PROGRAMS FOR THERMO-TECHNICAL CHARACTERISTICS DETERMINATION OF NUCLEAR-POWER REACTOR AND PRIMARY CIRCUIT OF VVER-440 NUCLEAR-POWER PLANT (OF PWR-TYPE)
    GESE, A
    ARBET, L
    JADERNA ENERGIE, 1980, 26 (11): : 421 - 430
  • [23] Experience in introducing systems of vibration diagnostics of the equipment at nuclear power stations with VVER-440 reactors
    Anikin, G.G.
    Pavelko, V.I.
    Thermal Engineering, 1999, 46 (06): : 445 - 452
  • [24] MODEL OF ACCUMULATION OF RADIONUCLIDES IN BOILER WATER OF STEAM-GENERATORS IN NUCLEAR-PLANTS WITH VVER-440 AND VVER-1000 REACTORS
    IVANOV, EA
    PYRKOV, IV
    KHAMYANOV, LP
    ATOMIC ENERGY, 1994, 77 (01) : 549 - 553
  • [25] Experience in introducing systems of vibration diagnostics of the equipment at nuclear power stations with VVER-440 reactors
    VNIIAES, Moscow, Russia
    Teploenergetika, 1999, 46 (06): : 12 - 17
  • [26] FEASIBILITY AND USEFULNESS OF RECONSTRUCTING OBSOLETE POWER BLOCKS OF VVER-440 REACTORS
    KIRICHENKO, AM
    KRUSHENIK, SD
    SIGAL, MV
    KUSTOV, VP
    ATOMIC ENERGY, 1993, 74 (01) : 32 - 35
  • [27] EFFICIENCY OF SERIES-MANUFACTURED 440 MW UNITS WITH VVER-440 WATER-MODERATED WATER-COOLED POWER-REACTORS AT NUCLEAR-POWER STATIONS
    KIRSH, GM
    KANAEV, VD
    POMERANTSEV, PI
    THERMAL ENGINEERING, 1975, 22 (09) : 62 - 67
  • [28] Primary Circuit Coolant Pressure and Quantity Control of a Nuclear Power Station with VVER-440 Reactor.
    Kowalski, Krzysztof
    Przeglad Elektrotechniczny, 1980, 56 (05): : 227 - 230
  • [29] A NEW SIMULATION CODE FOR ANALIZING LOSS OF COOLANT ACCIDENTS IN VVER-440/213 REACTORS CONCERNING ACTIVITY TRANSPORT
    Madaras, Attila
    Deme, Sandor
    Hozer, Zoltan
    Lang, Edit
    Nemeth, Istvan
    Pazmandi, Tamas
    Szanto, Peter
    PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 2, 2009, : 471 - 476
  • [30] Mossbauer study of corrosion products from VVER-440 nuclear power plant Bohunice
    Sluge, V
    Lipka, J
    Tóth, I
    Zeman, A
    Uváik, P
    Hasík, J
    Hinca, R
    Lehota, M
    JAHRESTAGUNG KERNTECHNIK 2000 - ANNUAL MEETING ON NUCLEAR TECHNOLOGY 2000, 2000, : 601 - 604
12345