EFFECT OF THE QUANTITY, COMPOSITION, AND THICKNESS OF DEPOSITS ON THE DAMAGE TO THE PIPES OF STEAM GENERATORS IN NUCLEAR POWER PLANTS WITH WER REACTORS

S. G. Oleinik

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EFFECT OF THE QUANTITY, COMPOSITION, AND THICKNESS OF DEPOSITS ON THE DAMAGE TO THE PIPES OF STEAM GENERATORS IN NUCLEAR POWER PLANTS WITH WER REACTORS

机译：反应堆核电厂中沉积物的数量，组成和厚度对蒸汽发生器管道损伤的影响

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摘要

The mechanism of corrosion damage to the heat-transfer pipes of steam generators and the effect of the composition, thickness, and quantity of deposits on the risk of damage to the piping of steam generators are examined.

机译：研究了蒸汽发生器传热管的腐蚀损坏机理以及沉积物的组成，厚度和数量对蒸汽发生器管道损坏风险的影响。

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来源
《Atomic Energy》 |2004年第4期|p.228-233|共6页
作者
S. G. Oleinik;
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作者单位

Experimental Scientific-Research Center;

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收录信息美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
原文格式 PDF
正文语种 eng
中图分类原子能技术;
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1. Erosion—Corrosion Entrainment of Iron-Containing Compounds as a Source of Deposits in Steam Generators Used at Nuclear Power Plants Equipped with WER Reactors [J] . G. V. Tomarov, A. A. Shipkov Thermal engineering . 2011,第3期

机译：侵蚀—含铁化合物作为配备有WER反应堆的核电厂所用蒸汽发生器中的沉积物来源的腐蚀夹带
2. INFLUENCE OF VARIOUS FACTORS ON DAMAGE TO STEAM-GENERATOR TUBES IN NUCLEAR POWER PLANTS WITH WER REACTORS [J] . S. G. Oleinik Atomic Energy . 2004,第6期

机译：各种因素对带有核反应堆的核电厂蒸汽发生器管损坏的影响
3. Measures for Ensuring Reliable Operation of the Welded Joint Connecting the Reactor Coolant Circuit's Header to the Shell of a Steam Generator Used at a WER-1000 Reactor-Based Nuclear Power Station [J] . S. A. Kharchenko, N. B. Trunov, N. F. Korotaev, Thermal engineering . 2011,第3期

机译：确保将反应堆冷却剂回路接头连接到WER-1000反应堆核电站使用的蒸汽发生器壳体的焊接接头可靠运行的措施
4. DESIGN ISSUES AND CONSIDERATIONS DURING REACTOR VESSEL HEAD REPLACEMENT, STEAM GENERATOR REPLACEMENT, AND STEAM GENERATOR SNUBBER ELIMINATION AT NUCLEAR POWER PLANTS [C] . Dilip Bhavnani, James Annett PVP-vol.480; American Society of Mechanical Engineers and Japan Society of Mechanical Engineers(ASME/JSME) Pressure Vessels and Piping Conference; 20040725-29; San Diego,CA(US) . 2004

机译：更换核反应堆中的反应堆容器头，更换蒸汽发生器和消除蒸汽发生器缓冲液期间的设计问题和注意事项
5. NUCLEAR POWER PLANT MODELING AND STEAM GENERATOR STABILITY ANALYSIS [D] . KORNFILT, JAK 1981

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6. Detection of alpha particle emitters originating from nuclear fuel inside reactor building of Fukushima Daiichi Nuclear Power Plant [O] . Yuki Morishita, Tatsuo Torii, Hiroshi Usami, -1

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8. Worldwide Assessment of Steam-Generator Problems in Pressurized-Water-Reactor Nuclear Power Plants [R] . Woo, H. H., Lu, S. C. 1981

机译：全球评估加压水反应堆核电厂蒸汽发生器问题

EFFECT OF THE QUANTITY, COMPOSITION, AND THICKNESS OF DEPOSITS ON THE DAMAGE TO THE PIPES OF STEAM GENERATORS IN NUCLEAR POWER PLANTS WITH WER REACTORS

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