EXPERIMENTAL ASSESSMENT OF THE EFFECTIVENESS OF RECOVERY ANNEALING OF WER-1000 VESSELS

Ya. I. Shtrombakh; B. A. Gurovich; E. A. Kuleshova; D. Yu. Erak; S. V. Fedotova; D. A. Zhurko; O. O. Zabusov; Yu. A. Nikolaev

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EXPERIMENTAL ASSESSMENT OF THE EFFECTIVENESS OF RECOVERY ANNEALING OF WER-1000 VESSELS

机译：WER-1000船的恢复退火效率的实验评估

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An experimental assessment of the effectiveness of recovery annealing of WER-1000 vessels on the basis of mechanical tests and structural studies of control samples of the main metal and the weld-seam metal with high nickel content (>1.65%) in the No. 1 unit of the Balakovo nuclear power plant in states after primary irradiation in the control sample channels, annealing in a chosen regime, and repeat accelerated irradiation in the IR-8 research reactor tofluence corresponding to extended service to 60 yr and longer is presented. The mechanical tests and structural studies showed a high degree of recovery of the structure and properties for the chosen temperature-time regime of annealing as well as a lower rate of repeated after the recovery annealing embrittlement as compared with the rate of embrittlement with primary irradiation.

机译：根据机械测试和1号镍含量高（> 1.65％）的主要金属和焊缝金属的控制样品的结构研究，对WER-1000容器的恢复退火效果进行实验评估。介绍了在控制样品通道中进行初次辐照，在选定的方案中进行退火，并在IR-8研究堆中重复加速辐照后各州巴拉科沃核电站的状态，相应的使用寿命延长至60年以上。力学测试和结构研究表明，与选定的退火温度时间方案相比，结构和性能的恢复程度高，与初始辐照时的脆化率相比，恢复脆化后的重复率更低。

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《Atomic Energy》 |2011年第4期|p.257-265|共9页
作者
Ya. I. Shtrombakh; B. A. Gurovich; E. A. Kuleshova; D. Yu. Erak; S. V. Fedotova; D. A. Zhurko; O. O. Zabusov; Yu. A. Nikolaev;
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作者单位

Institute of Reactor Materials and Technologies, Russian Science Center Kurchatov Institute, Moscow.;

Institute of Reactor Materials and Technologies, Russian Science Center Kurchatov Institute, Moscow.;

Institute of Reactor Materials and Technologies, Russian Science Center Kurchatov Institute, Moscow.;

Institute of Reactor Materials and Technologies, Russian Science Center Kurchatov Institute, Moscow.;

Institute of Reactor Materials and Technologies, Russian Science Center Kurchatov Institute, Moscow.;

Institute of Reactor Materials and Technologies, Russian Science Center Kurchatov Institute, Moscow.;

Institute of Reactor Materials and Technologies, Russian Science Center Kurchatov Institute, Moscow.;

Institute of Reactor Materials and Technologies, Russian Science Center Kurchatov Institute, Moscow.;

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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);
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正文语种 eng
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入库时间 2022-08-18 00:40:08

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1. Experimental investigation of in-vessel mixing phenomena in a WER-1000 scaled test facility during unsteady asymmetric transients [J] . A. Bucalossi, F. Moretti, D.Melideo, Nuclear Engineering and Design . 2011,第8期

机译：非稳态非对称瞬态过程中WER-1000规模测试设备中容器内混合现象的实验研究
2. MECHANISM OF CHANGE IN VVER-440, -1000 VESSEL MATERIAL PROPERTIES IN IRRADIATION-RECOVERY ANNEALING-IRRADIATION CYCLE [J] . B. A. Gurovich, E. A. Kuleshova, D. A. Mal’tsev, Atomic Energy . 2018,第2期

机译：辐照-恢复-退火-辐照循环中VVER-440，-1000容器材料特性的变化机理
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机译：Cr-Mo-V型压力容器钢的辐照脆化和恢复退火机理
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机译：由于反应堆压力容器钢的退火导致的脆化恢复模型

EXPERIMENTAL ASSESSMENT OF THE EFFECTIVENESS OF RECOVERY ANNEALING OF WER-1000 VESSELS

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