Evolution of microstructure after irradiation creep in several austenitic steels irradiated up to 120 dpa at 320 degrees C

Renault-Laborne A.; Garnier J.; Malaplate J.; Gavoille P.; Sefta F.; Tanguy B.

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Evolution of microstructure after irradiation creep in several austenitic steels irradiated up to 120 dpa at 320 degrees C

机译：几种奥氏体钢在320摄氏度下辐照至120 dpa的辐射蠕变后的微观组织演变

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Irradiation creep was investigated in different austenitic steels. Pressurized tubes with stresses of 127 -220 MPa were irradiated in BOR-60 at 320 degrees C to 120 dpa. Creep behavior was dependent on both chemical composition and metallurgical state of steels.

机译：研究了不同奥氏体钢的辐照蠕变。在BOR-60中于320摄氏度至120 dpa的压力下辐照压力为127 -220 MPa的加压管。蠕变行为取决于钢的化学成分和冶金状态。

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《Journal of Nuclear Materials: Materials Aspects of Fission and Fusion》 |2016年第null期|共18页
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Renault-Laborne A.; Garnier J.; Malaplate J.; Gavoille P.; Sefta F.; Tanguy B.;
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1. Evolution of microstructure after irradiation creep in several austenitic steels irradiated up to 120 dpa at 320 degrees C [J] . Renault-Laborne A., Garnier J., Malaplate J., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2016,第Null期

机译：几种奥氏体钢在320摄氏度下辐照至120 dpa的辐射蠕变后的微观组织演变
2. Void swelling and irradiation creep of two high-nickel steels after irradiation at 400-410 degrees C to 84-91 dpa in the BN-350 fast reactor [J] . Porollo SI., Vorobjev AN., Konobeev YV., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2000,第Pta1期

机译：BN-350快堆中两种高镍钢在400-410摄氏度至84-91 dpa辐照后的空隙膨胀和辐照蠕变
3. The comparison of microstructure and nanocluster evolution in proton and neutron irradiated Fe-9%Cr ODS steel to 3 dpa at 500 degrees C [J] . Swenson M. J., Wharry J. P. Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2015,第Pta1期

机译：质子和中子辐照Fe-9％Cr ODS钢至500摄氏度下3 dpa的微观结构和纳米簇演化的比较
4. MICROSTRUCTURE AND GRAIN BOUNDARY CHEMISTRY EVOLUTION IN AUSTENITIC STAINLESS STEELS IRRADIATED IN THE BOR-60 REACTOR UP TO 120 DPA [C] . Alexandra-Evelyne Renault, Cedric Pokor, Jerome Gamier, International conference on environmental degradation of materials in nuclear power systems water reactors . 2010

机译：BOR-60反应器中高达120 DPA辐照的奥氏体不锈钢的微观结构和晶粒边界化学变化
5. Microstructure evolution in proton -irradiated austenitic Fe-Cr-Ni alloys under LWR core conditions [D] . Gan, Jian 1999

机译：轻水堆芯条件下质子辐照奥氏体Fe-Cr-Ni合金的组织演变
6. Microstructure Evolution and Mechanical Properties of Tempered 5140 Alloy Steel after Proton Irradiation at Different Temperatures [O] . Luanyue Dai, Guangyi Niu, Mingzhen Ma 2020

机译：不同温度质子辐照后温度5140合金钢的微观结构演化与力学性能
7. Creep and Fatigue at Elevated Temperatures. Study on Creep-Fatigue Life of Irradiated Austenitic Stainless Steel. [O] . Ikuo IOKA, Yukio MIWA, Hirokazu TSUJI, 2002

机译：在升高的温度下蠕变和疲劳。辐照奥氏体不锈钢蠕变疲劳寿命研究。

Evolution of microstructure after irradiation creep in several austenitic steels irradiated up to 120 dpa at 320 degrees C

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