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| STUDY ON THE MICROSTRUCTURE EVOLUTION OF A508–3 STEEL UNDER PROTON IRRADIARION |
| WAN Qiangmao 1,2, SHU Guogang 1,3, WANG Rongshan 2, DING Hui 1, PENG Xiao 1,2, ZHANG Qi 1, LEI Jing 1 |
1. School of Power and Mechanical Engineering, Wuhan University, Wuhan 430072
2. Suzhou Nuclear Power Research Institute Co., Ltd., Suzhou 215004
3. China Nuclear Power Engineering Co., Ltd., Shenzhen 518031 |
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Cite this article:
WAN Qiangmao SHU Guogang WANG Rongshan DING Hui PENG Xiao ZHANG Qi LEI Jing . STUDY ON THE MICROSTRUCTURE EVOLUTION OF A508–3 STEEL UNDER PROTON IRRADIARION. Acta Metall Sin, 2012, 48(8): 929-934.
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Abstract Irradiation embrittlement of reactor pressure vessel (RPV) steels is one of the critical issues for integrity and safety in long–life operation of light water reactors. The embrittlement is attributed to three main nano–scale microstructural features including copper rich precipitates, matrix damage and grain boundary segregation. The relevance of matrix component of damage can be high in low copper content alloys and also in the case of high doses. Some recent works have been done in trying to clarify the exact nature of this component of the damage in irradiated commercial steels. This is still an open question: how the irradiation–induced microstructure will evolve in the A508–3 steel in the high dose range. In the present work, in order to emulate the neutron irradiation damage in the RPV steels, 190 keV proton irradiations were conducted on a A508–3 steel to 0.108, 0.216 and 0.271 dpa at room temperature. The irradiation –induced microstructure was examined by TEM. The obtained results show that the irradiation induced defects are mainly dislocation loops, majority of which are both of <100> type and of interstitial type, without the observation of the micro–voids. Dislocation loops distribute roughly evenly in the matrix, and some dislocation loops decorate the pre–existing dislocation lines. As the irradiation dose increase, the average diameter of dislocation loops increase and the size distribution of dislocation loops become broader. As the dose increased from 0.108 dpa to 0.216 dpa and 0.271 dpa, the average diameter of loops increase from about 1.8 nm to about 3.0 and about 4.6 nm, the number density of loops are in the order of 1022 m−3 with an weak increasing trend. The formation mechanism of dislocation loops and the effect of dose on hardening and embrittlement were discussed. Irradiation–induced dislocation loops cause hardening and embrittlement in the A508–3 steel, which would not saturate at the studied dose range. The dose dependence of yield strength increment and transition temperature shift follows a power law.
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Received: 13 February 2012
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| Fund: Supported by National Science and Technology Major Project (No.2011ZX06004) |
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