Experimental Study on Low-Cycle Fatigue Properties of Supercritical Water-cooled Reactor Candidate Cladding Material

被引：0

作者：

Zhao Y. ^{[1
,2
]}

Xiong R. ^{[1
]}

Liang B. ^{[1
]}

Tang R. ^{[1
]}

机构：

[1] Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu

[2] Polymer Research Institute, Sichuan University, Chengdu

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2023年 / 44卷 / 05期

关键词：

Cladding tube; Curve; Low cycle fatigue; Stainless steel; Supercritical water-cooled reactor (SCWR);

D O I：

10.13832/j.jnpe.2023.05.0237

中图分类号：

学科分类号：

摘要：

In order to obtain the low cycle fatigue performance data of 20Cr-25Ni, a candidate cladding material for supercritical water cooled reactor (SCWR), and to provide technical reference for the design, development and engineering of SCWR, the low cycle fatigue tests of 20Cr-25Ni at room temperature, 500℃, 650℃ and 800℃ were carried out on MTS809 testing machine, and the multi-level cyclic hysteresis curve, cyclic stress-strain curve, the relationship curve between stress amplitude and cyclic fraction, cyclic stress-strain model and low cycle fatigue Manson-Coffin model parameters were obtained. The results of low cycle fatigue test of 20Cr-25Ni show that the fatigue resistance of 20Cr-25Ni stainless steel pipe decreases with the increase of temperature, and shows obvious cyclic hardening at 500℃ and 650℃. Therefore, the cladding material has good fatigue resistance below 650℃. When the maximum core temperature of SCWR is higher than 650℃, it is necessary to be careful to use this material as cladding material. © 2023 Yuan Zi Neng Chuban She. All rights reserved.

引用

页码：237 / 243

页数：6

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