DESIGN PROVISIONS FOR OPERATIONAL CAPABILITY OF A NUCLEAR-POWER PLANT WITH A HIGH-POWERED WATER-COOLED CHANNEL REACTOR IN EMERGENCY REGIMES

被引:2
|
作者
EMELYANOV, IY
KUZNETSOV, SP
CHERKASHOV, YM
机构
来源
SOVIET ATOMIC ENERGY | 1981年 / 50卷 / 04期
关键词
D O I
10.1007/BF01121112
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:226 / 230
页数:5
相关论文
共 27 条
  • [1] STATE OF METALLIC SURFACES IN SYSTEMS OF NUCLEAR-POWER PLANTS WITH A SERIES 1000 HIGH-POWERED - WATER-COOLED CHANNEL REACTOR AFTER ASSEMBLY
    SEDOV, VM
    KRUTIKOV, PG
    GRUSHANIN, AI
    ZOLOTUKHIN, ST
    ZAKHARZHEVSKII, YO
    EPERIN, AP
    SOVIET ATOMIC ENERGY, 1981, 50 (03): : 164 - 166
  • [2] SOME CHARACTERISTICS OF AND EXPERIENCE WITH THE OPERATION OF NUCLEAR-POWER PLANTS WITH RBMK-1000 HIGH-POWERED WATER-COOLED CHANNEL REACTORS (RBMK)
    DOLLEZHAL, NA
    EMELYANOV, IY
    CHERKASHOV, YM
    VASILEVSKII, VP
    PODLAZOV, LN
    POSTNIKOV, VV
    SIROTKIN, AP
    KEVROLEV, VP
    KRAMEROV, AY
    SOVIET ATOMIC ENERGY, 1983, 54 (04): : 263 - 269
  • [3] DEFORMATION OF AN ENERGY-RELEASE FIELD IN A HIGH-POWERED WATER-COOLED CHANNEL REACTOR (RBMK)
    ALEKSAKOV, AN
    VORONTSOV, BA
    EMELYANOV, IY
    PODLAZOV, LN
    RYABOV, VI
    SVECHAREVSKII, BM
    SOVIET ATOMIC ENERGY, 1979, 46 (04): : 267 - 273
  • [4] OPTIMIZATION OF THE SAFETY MARGIN TO THE CRITICAL LOAD OF THE HEAT-RELEASING ASSEMBLIES IN A HIGH-POWERED WATER-COOLED CHANNEL REACTOR (RBMK)
    BRYUNIN, SV
    GORELOV, AI
    NOVIKOV, VY
    PAVLOV, IK
    POSTNIKOV, VV
    SOVIET ATOMIC ENERGY, 1979, 46 (04): : 262 - 267
  • [5] CHANGE IN THE FUEL COMPONENT OF THE COST OF ELECTRICAL ENERGY DURING A TRANSITIONAL OPERATING PERIOD OF A HIGH-POWERED WATER-COOLED CHANNEL REACTOR (RBMK)
    BRYUNIN, SV
    ZHIRNOV, AD
    PUSHKAREV, VI
    RUNIN, VI
    SOVIET ATOMIC ENERGY, 1979, 46 (04): : 259 - 262
  • [6] DESIGNING A NUCLEAR-POWER STATION WITH 1000 MW WATER-MODERATED WATER-COOLED REACTOR UNITS
    BERKOVICH, VM
    KALOSHIN, YP
    TATARNIKOV, VP
    SHENDEROVICH, AS
    THERMAL ENGINEERING, 1974, 21 (04) : 22 - 27
  • [7] Conceptual design of a high temperature water-cooled divertor for a fusion power reactor
    Giancarli, L
    Bonal, JP
    Puma, AL
    Michel, B
    Sardain, P
    Salavy, JF
    FUSION ENGINEERING AND DESIGN, 2005, 75-79 : 383 - 386
  • [8] HIGH-POWER STEAM GENERATORS FOR NUCLEAR-POWER STATIONS WITH WATER-COOLED WATER-MODERATED REACTORS
    TITOV, VF
    SUPRUNOV, VG
    TARANKOV, GA
    STEKOLNI.VV
    DENISOV, VP
    GRISHAKO.VI
    SOVIET ATOMIC ENERGY-USSR, 1971, 30 (02): : 219 - &
  • [9] MULTICHANNEL CORRELATION SYSTEM FOR MEASUREMENT OF THE COOLANT FLOW-RATE FOR HIGH-POWERED WATER-COOLED CHANNEL REACTORS (RBMK)
    SELIVANOV, VM
    LYSIKOV, BV
    KARLOV, NP
    KUZNETSOV, BA
    MARTYNOV, AD
    PROSTYAKOV, VV
    PALLAGI, D
    KHORANI, S
    KHARGITAI, T
    TEZHER, S
    SOVIET ATOMIC ENERGY, 1984, 56 (02): : 70 - 74
  • [10] The interaction of nuclear reactor core melt with oxide sacrificial material of localization device for a nuclear power plant with water-moderated water-cooled power reactor
    V. G. Asmolov
    A. A. Sulatskii
    S. V. Beshta
    V. S. Granovskii
    V. B. Khabenskii
    E. V. Krushinov
    S. A. Vitol’
    V. I. Al’myashev
    V. V. Gusarov
    V. F. Strizhov
    High Temperature, 2007, 45 : 22 - 31