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Coolant technology of water cooled reactors. V. 2: Corrosion in the primary coolant systems of water cooled reactors.

机译：水冷反应堆的冷却技术。 V. 2：水冷反应堆的主冷却剂系统的腐蚀。

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The articles of this volume discuss corrosion in the primary coolant systems of water cooled reactors. Refs, figs and tabs. (Atomindex citation 24:007246)

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年度 1992
页码 1-73
总页数 73
原文格式 PDF
正文语种 eng
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Primary Coolant Circuits; Corrosion; BWR Type Reactors; Corrosion Products; PHWR Type Reactors; PWR Type Reactors; Foreign technology; EDB/210200; EDB/210100; EDB/210400;

机译：主冷却剂回路;腐蚀; BWR型反应器;腐蚀产物; pHWR型反应器; pWR型反应器;国外技术; EDB / 210200; EDB / 210100; EDB / 210400;

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1. Measurement Instruments for Automatically Monitoring the Water Chemistry of Reactor Coolant at Nuclear Power Stations Equipped with VVER Reactors. Selection of Measurement Instruments and Experience Gained from Their Operation at Russian and Foreign NPSs [J] . Yu. A. Ivanov Thermal engineering . 2007,第12期

机译：用于自动监测配备VVER反应堆的核电站反应堆冷却剂水化学的测量仪器。在俄罗斯和国外NPS上选择测量仪器和从中获得的经验
2. Corrosion Behavior of 3A21 Aluminum Alloy in Water- Ethylene Glycol Coolant under Simulated Engine Working ConditionsCorrosion Behavior of 3A21 Aluminum Alloy in Water- Ethylene Glycol Coolant under Simulated Engine Working Conditions [J] . Hanyang Zuo, Jinlong Fan, Feng Liu, International Journal of Electrochemical Science . 2021,第6期

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3. Keep good coolant from going bad: combining proven filtration systems with new technologies helps shops clean up water-soluble coolant and reduce costs [J] . Carney Likens, Parker Hannifin Corp American Machinist . 2000,第4期

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4. Corrosion in Liquid Cooling Systems with Water-Based Coolant – Part 2: Corrosion Reliability Testing and Failure Model [C] . Choong-Un Kim, Geng Ni, Girish Kini, IEEE Intersociety Conference on Thermal and Thermomechanical Phenomena in Electronic Systems . 2020

机译：带水基冷却剂的液体冷却系统中的腐蚀–第2部分：腐蚀可靠性测试和失效模型
5. The effects of boric acid on corrosion of steels in simulated pressurized water reactor primary coolant. [D] . Pongpuak, Janit. 2007

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6. Fukushima-derived radionuclides in sediments of the Japanese Pacific Ocean coast and various Japanese water samples (seawater tap water and coolant water of Fukushima Daiichi reactor unit 5) [O] . Katsumi Shozugawa, Beate Riebe, Clemens Walther, -1

机译：日本太平洋沿岸沉积物和各种日本水样（福岛第一核反应堆5的海水自来水和冷却水）中来自福岛的放射性核素
7. LABORATORY SIMULATIONS OF CLADDING-STEAM REACTIONS FOLLOWING LOSS-OF- COOLANT ACCIDENTS IN WATER-COOLED POWER REACTORS. [O] . Hesson, J.C., Ivins, R.O., Wilson, R.E., 1970

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8. Fuel Cladding Interaction with Water Coolant in Power Reactors. A Survey Report of a Coordinated Research Programme on the Investigation of Fuel Element Cladding Interaction with Water Coolant in Power Reactors [R] . Silva Galetti, M. R., Pontedeiro, A. C., Camargo, C. T. M. 1985

机译：燃料熔覆与动力堆水冷却剂的相互作用。电力反应堆燃料元件与水冷却剂相互作用研究协调研究计划的调查报告

Coolant technology of water cooled reactors. V. 2: Corrosion in the primary coolant systems of water cooled reactors.

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