DEACTIVATION OF NUCLEAR POWER PLANT (NPP) EQUIPMENT WITH VVER-440 REACTORS.

被引：0
|
作者：
Balaban-Irmenin, Yu.V.
Teplitskii, A.L.
机构：
来源：
Soviet power engineering | 1981年 / 10卷 / 04期
关键词：
ETCHING - POTASSIUM COMPOUNDS;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
Soviet and GDR specialists developed a new technology for deactivation of the primary circuit. Dissolution of the oxide film, including radio-potassium permanganate and an etching solution of ethylenediaminetetraacetic and citric acid. Initial testing of the new technology carried out in 1978, during deactivation of the primary circuit of a standard energy unit with the VVER-440 reactor.
引用
收藏
页码：501 / 506
相关论文
共 50 条
  • [31] Predicting growth of deposits on fuel assemblies of VVER-440 reactors
    Kritskii V.G.
    Rodionov Y.A.
    Berezina I.G.
    Fedorov A.I.
    Vitkovskii S.L.
    Shchedrin M.G.
    Galanin A.V.
    Slobodov A.A.
    Thermal Engineering, 2009, 56 (05) : 387 - 389
  • [32] Conservative evaluation of radionuclides release for VVER-440 and VVER-1000 type reactors
    Berezhnyi, A.
    Krushynskyi, A.
    Ruban, D.
    Sholomitsky, S.
    ANNALS OF NUCLEAR ENERGY, 2023, 194
  • [33] Optoelectronic devices "Control" for noncontact dimensional inspection of fuel elements of nuclear reactors VVER-1000 and VVER-440
    Beloglazova, VA
    Bitytsky, OI
    Chapaev, IG
    Chernyshov, VM
    Chugui, YV
    Gushchina, AA
    Karlov, YK
    Krivenkov, BE
    Ladygin, VI
    Nesin, VI
    Pastushenko, AI
    Pimenov, YV
    Rozhkov, VV
    Yunoshev, SP
    Yunoshev, VP
    SEVENTH INTERNATIONAL SYMPOSIUM ON LASER METROLOGY APPLIED TO SCIENCE, INDUSTRY, AND EVERYDAY LIFE, PTS 1 AND 2, 2002, 4900 : 659 - 668
  • [34] DESIGN REVIEW OF THE VVER-440 NPP MAIN COMPONENTS ON THE BASE OF ASME BPVC
    Boros, Janos
    Palfi, Tamas
    Palfi, Peter
    Ratkai, Sandor
    ASME PRESSURE VESSELS AND PIPING CONFERENCE, VOL 7: OPERATIONS, APPLICATIONS AND COMPONENTS, 2010, : 501 - 507
  • [35] RAISING POWER LEVELS AT VVER-440 POWER-STATIONS
    PROSELKOV, VN
    SIMONOV, KV
    SPASSKOV, VP
    PYTKIN, YN
    KODANEV, SA
    VIDENEEV, EN
    PANASHCHENKO, NS
    ANDRUSHECHKO, SA
    MATVEEV, AA
    LITVINOV, AN
    SOVIET ATOMIC ENERGY, 1990, 69 (02): : 634 - 636
  • [36] Residual lifetime assessment of the VVER-440 RPV support structure of Kozloduy NPP
    Kirilova, Desislava
    Ilieva, Krassimira
    Belousov, Sergey
    COMPTES RENDUS DE L ACADEMIE BULGARE DES SCIENCES, 2008, 61 (06): : 713 - 720
  • [37] Nuclear Power Plant Developments with Thermal Reactors.
    Koenig, Hans Hermann
    Atom und Strom, 1976, 22 (01): : 1 - 14
  • [38] RELIABILITY OF HIGH-PRESSURE RECOVERY-SYSTEM IN THE POWER-GENERATING UNITS OF NUCLEAR-POWER-PLANTS WITH VVER-1000 AND VVER-440 NUCLEAR-REACTORS
    BARANENKO, VI
    PIONTKOVSKII, AI
    KHMARYUK, SP
    DAVIDENKO, NN
    SHALAEV, AG
    KUKHAREV, ND
    VORONTSOV, EO
    ERMOLAEV, AV
    ZAKHAROV, VA
    KUKHAREV, AF
    ATOMIC ENERGY, 1995, 78 (02) : 129 - 135
  • [39] Automatic loading pattern optimization tool for Loviisa VVER-440 reactors
    Kuopanportti, J.
    KERNTECHNIK, 2013, 78 (04) : 292 - 299
  • [40] Investigation of Primary Circuit Loop Transfer Properties in VVER-440 reactors
    Kiss, Sandor
    Lipcsei, Sandor
    22ND INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2013), 2013,
12345