Composite nozzle dam in the steam generator of a nuclear reactor

Je Hoon Oh; Dai Gil Lee; Tae Ryong Kim

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Composite nozzle dam in the steam generator of a nuclear reactor

机译：核反应堆蒸汽发生器中的复合喷嘴坝

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The period of normal shutdown and maintenance for a nuclear power plant can be remarkably shortened when the examination and maintenance of the tubes of a steam generator are simultaneously carried out with refueling. The nozzle dam in a steam generator is a closure to block the flow of coolant from the inlet-outlet nozzles in a steam generator. Recently, the installation and removal operations of the nozzle dam were attempted using a robot rather than the manual operation because of the radioactive hazard. For the operation using the robot the weight of the dam must be reduced because the robot's payload for assembling operations is usually small.

机译：当在加油的同时对蒸汽发生器的管道进行检查和维护时，可以大大缩短核电站的正常停工和维护周期。蒸汽发生器中的喷嘴挡板是一个封闭装置，用于阻止冷却剂从蒸汽发生器中的入口喷嘴流出。最近，由于放射性危害，试图用机器人而不是手动操作来安装和拆卸喷嘴坝。对于使用机器人的操作，必须减轻水坝的重量，因为组装操作时机器人的有效载荷通常很小。

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来源
《Composite Structures》 |1997年第4期|p.203-213|共11页
作者
Je Hoon Oh; Dai Gil Lee; Tae Ryong Kim;
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收录信息美国《科学引文索引》(SCI);美国《工程索引》(EI);
原文格式 PDF
正文语种 eng
中图分类工程材料学;
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1. Specific Features of Corrosion Damage to Heat-Transfer Tubes of Steam Generators Used at Nuclear Power Stations Equipped with VVER-1000 Reactors [J] . D. S. Nemytov, V. F. Tyapkov Thermal engineering . 2009,第7期

机译：配备VVER-1000反应堆的核电站所用蒸汽发生器的传热管的腐蚀损坏的特殊特征
2. 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 [J] . S. G. Oleinik Atomic Energy . 2004,第4期

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
3. 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
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. Environmentally induced cracking in Alloy 600 and SA 302 steel in pressurized water reactor steam generator conditions. [D] . Rebak, Raul Basilio. 1993

机译：在压水堆蒸汽发生器条件下，合金600和SA 302钢在环境中引起的开裂。
6. A novel inspection robot for nuclear station steam generator secondary side with self-localization [O] . Jinke Li, Xinyu Wu, Tiantian Xu, -1

机译：具有自定位功能的新型核电站蒸汽发生器二次侧检查机器人
7. Estimation of damage risks for the weld assembly between the header and the steam generator nozzle in a WWER NPP [O] . N.N. Netyaga, S.P. Saakyan, V.P. Povarov 2017

机译：估算WWER Npp中集管和蒸汽发生器喷嘴之间焊接组件的损坏风险
8. Numerical Simulation of Steam Separators Used in Nuclear Steam Generators and Reactor Systems. Volume 2. User's Manual [R] . Vander Vorst, M. J. 1983

机译：核电蒸汽发生器和反应器系统用蒸汽分离器的数值模拟。第2卷。用户手册

Composite nozzle dam in the steam generator of a nuclear reactor

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