Operational reliability analysis of power unit fast sodium reactor BN-600 for period 1980-1990 years

被引：0
|
作者：
Oshkanov, N.N.
Shejnkman, A.G.
Govorov, P.P.
机构：
来源：
Atomnaya Energiya | 1994年 / 76卷 / 03期
关键词：
Reactor operation reliability;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
引用
收藏
页码：167 / 171
相关论文
共 14 条
  • [1] ANALYSIS OF THE OPERATIONAL RELIABILITY OF A POWER-GENERATING UNIT WITH A BN-600 REACTOR DURING THE PERIOD 1980-1993
    OSHKANOV, NN
    SHEINKMAN, AG
    GOVOROV, PP
    ATOMIC ENERGY, 1994, 76 (03) : 165 - 169
  • [2] Raising the operational reliability of the steam generator of a BN-600 power unit in starting regimes
    Govorov P.P.
    Thermal Engineering, 2006, 53 (9) : 733 - 736
  • [3] 30 Years of experience in operating the BN-600 sodium-cooled fast reactor
    N. N. Oshkanov
    O. M. Saraev
    M. V. Bakanov
    P. P. Govorov
    O. A. Potapov
    Yu. M. Ashurko
    V. M. Poplavskii
    B. A. Vasil’ev
    Yu. L. Kamanin
    V. N. Ershov
    Atomic Energy, 2010, 108 : 234 - 239
  • [4] 30 YEARS OF EXPERIENCE IN OPERATING THE BN-600 SODIUM-COOLED FAST REACTOR
    Oshkanov, N. N.
    Saraev, O. M.
    Bakanov, M. V.
    Govorov, P. P.
    Potapov, O. A.
    Ashurko, Yu. M.
    Poplavskii, V. M.
    Vasil'ev, B. A.
    Kamanin, Yu. L.
    Ershov, V. N.
    ATOMIC ENERGY, 2010, 108 (04) : 234 - 239
  • [5] Operating experience with a power-generating unit with a BN-600 reactor
    Saraev, OM
    Oshkanov, NN
    Vylomov, VV
    Maltsev, VV
    Kochetkov, LA
    Troyanov, MF
    Bagdasarov, YE
    Poplavskii, VM
    Kiryushin, AI
    Kusavkov, NG
    Rogov, VA
    ATOMIC ENERGY, 1996, 80 (05) : 310 - 317
  • [6] Operation Experience with a Power-Generating Unit with a BN-600 Reactor
    At Energy, 5 (310):
  • [7] Operational studies of the thermohydraulic characteristics of steam generators in a BN-600 power-generating unit
    Sheinkman, A.G., 1600, (36):
  • [8] Plutonium disposition in the BN-600 fast-neutron reactor at the Beloyarsk nuclear power plant
    Moses, DL
    Chebeskov, AN
    Matveev, VI
    Vasiliev, BA
    Maltsev, VV
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 1998, 414 (01): : 28 - 35
  • [9] OPERATIONAL STUDIES OF THE THERMOHYDRAULIC CHARACTERISTICS OF STEAM-GENERATORS IN A BN-600 POWER-GENERATING UNIT
    SHEINKMAN, AG
    BELTYUKOV, AI
    VYLOMOV, VV
    KARPENKO, AI
    LYZHIN, AA
    SMIRNOV, MV
    KHALETSKII, EE
    THERMAL ENGINEERING, 1989, 36 (12) : 662 - 665
  • [10] Experience with Operational Chemical Washing of the Evaporators of the Steam Generators for Power Units with BN-600 and BN-350 Fast Reactors
    State Sci. Ctr. of the Russ. Fed., Energy Physics Institute , pl. Bondarenko 1, Obninsk 249020, Russia
    Therm Eng, 8 (633-638):
12