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Irradiation Response in Titanium-Modified Austenitic Stainless Steels Prepared by Rapid-Solidification Processing. Part 1. Microstructural Response to Neutron Irradiation

机译：快速凝固法制备钛改性奥氏体不锈钢的辐照响应。第1部分中子辐照的微结构响应

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The neutron irradiation response of cold worked Path A PCA has been investigated to about 34 dpa (3100 appm He). Cavity formation can be limited solely to helium accommodation in bubbles under certain circumstances, that is, with bias driven swelling completely suppressed. Under other conditions, however, similar behavior to that of type 316 steel is observed. The differences are strongly correlated with differences in the initial distribution of titanium carbide particles and their precipitation and/or recoil-induced dissolution under irradiation. The effects of rapid solidification processing are explored. (ERA citation 08:057296)

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Imeson, D.; Lee, M.; Vander Sande, J. B.; Grant, N. J.; Harling, O. K.;
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年度 1983
页码 1-7
总页数 7
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Austenitic Steels; Bubbles; Helium; Microstructure; Stainless Steel-316; Titanium Alloys; Titanium Carbides;

机译：奥氏体钢;气泡;氦;微观结构;不锈钢-316;钛合金;钛碳化物;

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1. Microstructural changes induced by post-irradiation annealing of neutron-irradiated austenitic stainless steels [J] . Cole JI., Allen TR. Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2000,第Pta1期

机译：中子辐照奥氏体不锈钢的辐照后退火引起的显微组织变化
2. Influence of temperature histories during reactor startup periods on microstructural evolution and mechanical properties of austenitic stainless steel irradiated with neutrons [J] . Kasahara Shigeki, Kitsunai Yuji, Chimi Yasuhiro, Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2016,第Null期

机译：反应堆启动期间的温度历史记录对中子辐照奥氏体不锈钢的组织演变和力学性能的影响
3. Microstructural origins of radiation-induced changes in mechanical properties of 316 L and 304 L austenitic stainless steels irradiated with mixed spectra of high-energy protons and spallation neutrons [J] . Sencer BH., Hamilton ML., Garner FA., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2001,第0期

机译：高能质子和散裂中子混合光谱辐照引起的316 L和304 L奥氏体不锈钢力学性能变化的微观组织起源
4. Void swelling and resultant strains in thick 304 stainless steel components in response to spatial gradients in neutron flux-spectra and irradiation temperature [C] . F. A. Garner, P. D. Freyer, D. L. Porter, International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors . 2016

机译：厚304不锈钢组分的空隙溶胀和合成菌株响应中子磁通光谱和辐照温度的空间梯度
5. The role of dislocation channeling in IASCC initiation of neutron irradiated austenitic stainless steel. [D] . Stephenson, Kale Jennings. 2016

机译：位错通道在中子辐照奥氏体不锈钢的IASCC引发中的作用。
6. Spectral and raw quasi in-situ energy dispersive X-ray data captured via a TEM analysis of an ODS austenitic stainless steel sample under 1 MeV Kr2+ high temperature irradiation [O] . Adam J. Brooks, Zhongwen Yao 2017

机译：在1MeV Kr2 +高温辐射下通过ODS奥氏体不锈钢样品的TEM分析获得的光谱和原始准原位能量色散X射线数据
7. Reactor Materials Program: Microstructural and mechanical response of Types 304, 304L, and 308 stainless steels to low temperature neutron irradiation. Task No. 89-023-1 [O] . R.L. Sindelar 1993

机译：反应器材料程序：304,304L和308型不锈钢的微观结构和机械响应，低温中子辐照。任务号89-023-1
8. Irradiation Response in Titanium-Modified Austenitic Stainless Steels Prepared by Rapid-Solidification Processing. Part 2. Dual-Ion Irradiations [R] . Tong, C. H., Imeson, D., Vander Sande, J. B., 1983

机译：快速凝固法制备钛改性奥氏体不锈钢的辐照响应。第2部分。双离子辐照

Irradiation Response in Titanium-Modified Austenitic Stainless Steels Prepared by Rapid-Solidification Processing. Part 1. Microstructural Response to Neutron Irradiation

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