Experience with Chemical Washings of a PGV-1000 Steam Generator When Cooling down the Reactor Installation

O.P.Arkhipov; S.I.Brykov; G.F.Banyuk

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Experience with Chemical Washings of a PGV-1000 Steam Generator When Cooling down the Reactor Installation

机译：冷却反应堆装置时对PGV-1000蒸汽发生器进行化学清洗的经验

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The procedure and results of chemical washings of PGV-1000 steam generators at power unit no.1 of the Khmel' nitsk nuclear power station(NPS)when cooling down the reactor installation are given. The prob- lem of improving the efficiency of removing iron-and copper-oxide deposits is discussed.

机译：给出了冷却反应堆装置时，在赫梅尔尼茨克核电站（NPS）1号机组的PGV-1000蒸汽发生器进行化学清洗的程序和结果。讨论了提高去除铁氧化物和铜氧化物沉积物效率的问题。

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《Thermal engineering》 |2000年第2期|p.152-155|共4页
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O.P.Arkhipov; S.I.Brykov; G.F.Banyuk;
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正文语种 eng
中图分类发电、发电厂;
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1. GRAVITATIONAL SEPARATION IN HORIZONTAL PGV-1000 STEAM GENERATORS IN NUCLEAR POWER PLANTS WITH VVER REACTORS [J] . V. I. Gorburov, A. Yu. Petrov, A. G. Zhukov, Atomic Energy . 2005,第6期

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2. Development of Mathematical Models for Substantiating the Safety of Nuclear Power Stations and an Analysis of the Dynamics of Accidents Associated with Intercircuit Leaks in the Steam Generators of Reactor Installations with Lead-Bismuth Coolant [J] . A. V. Dedul, I. S. Krasko Thermal engineering . 2006,第1期

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3. Steam generator test facility-A test bed for steam generators of Indian sodium cooled fast breeder reactors [J] . V.A. Suresh Kumar, I.B. Noushad, K.K. Rajan Nuclear Engineering and Design . 2012,第JULa期

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4. STEAM GENERATOR SECONDARY SIDE CHEMICAL CLEANING DURING REACTOR PLANT COOLING DOWN [C] . XIA Xiaojiao, WEN Juhua, MA Weigang International conference on nuclear engineering . 2014

机译：反应釜冷却过程中的蒸汽发生器二次侧化学清洗
5. Steam-Reheat Option for Supercritical-Water-Cooled Reactors. [D] . Saltanov, Eugene. 2010

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6. Chemically Activated Cooling Vest’s Effect on Cooling Rate Following Exercise-Induced Hyperthermia: A Randomized Counter-Balanced Crossover Study [O] . Yuri Hosokawa, Luke N. Belval, William M. Adams, 2020

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7. Evaluation of a Sodium–Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor [O] . Sang June Ahn, Kwi-Seok Ha, Won-Pyo Chang, 2016

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8. Steam Generator Tube Performance. Experience with Water-Cooled Nuclear Power Reactors During 1982 [R] . Tatone, O. S., Pathania, R. S. 1984

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Experience with Chemical Washings of a PGV-1000 Steam Generator When Cooling down the Reactor Installation

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