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[会议论文] 作者：Farong Wan,Jin Gao,Jie Li,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
The behavior of irradiation to hydrogen bubbles in materials would be an interesting question not only for fusion reactor materials,but also for common condensed matter physics.For example,sonolumines...
[会议论文] 作者：Jinsheng Li,Yufeng Du,Farong Wan,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
At the end of 1980s,Japanese scholars unexpectedly observed single crystal changed into polycrystals in deuterium-implanted aluminum under electron irradiation,but never be found in the case of electr...
[会议论文] 作者：Yuchen Liu,Wei Wei,Farong Wan,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
Cable-in-conduit conductors(CICC)structure is designed for ITER superconducting magnets,and the austenitic stainless steel is the leading candidate of jacket materials.In this paper,TEM and SEM with E...
[会议论文] 作者：Wei Wei,Yi Long,Farong Wan,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
For outstanding mechanical properties,the amorphous materials attracted the interests of scientists all over the world in recent years.Compared to corresponding crystalline alloys,the strength,hardnes...
[会议论文] 作者：Weiguang Yang,Qingwei Chen,Farong Wan,Dongsheng Xu,
来源：The 60th Annual Meeting of The International Society of Elec 年份：2009
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Influence of high-temperature ion irradiation on microstructures of the deformed and heat-treated V-
[会议论文] 作者：Jianwen Ding,Shanwu Yang,Boling Zhu,Yi Long,Farong Wan,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
As one of candidate structure materials for future fusion reactors,vanadium alloy has been widely studied in recent decades.In the present investigation,an attempt has been made to maintain mechanical...
[会议论文] 作者：Xing Qin,Yu Lei,Farong Wan,Liubiao Chen,Junjie Wang,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
A low temperature metallographic in-situ observation apparatus is designed to research the martensitic phase transformation of CuAlMn cryogenic shape memory alloy,and some changing characteristics is...
[会议论文] 作者：Yumei Jia,Pingping Liu,Wen Hu,Qian Zhan,Farong Wan,Jianli Zhang,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
The Helium Cooled Ceramic Breeder(HCCB)blanket that will be tested in ITER under the form of Test Blanket Modules(TBMs)located in a common equatorial port o...
[会议论文] 作者：Wentuo Han,Kiyohiro Yabuuchi,Pingping Liu,Xiaoou Yi,Farong Wan,Akihiko Kimura,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
Dissimilar joining of oxide dispersion strengthened(ODS)steel and reduced activation ferritic/martensitic(RAFM)steel would be required for the construction of advanced reactors to increase the flexibl...
[会议论文] 作者：Yufeng Du,Jin Gao,Pingping Liu,Wentuo Han,Xiaoou Yi,Farong Wan,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
A new kind of irradiation experiment method,which is an approximate in-situ method to study the grain boundary during irradiation,is proposed in the present study.Using this method,the irradiated and...
[期刊论文] 作者：Shaoning JIANG,Farong WAN,Yi LONG,Jianchao HE,Pingping LIU,Somei OHNUKI,Naoyuki HASHIMOTO,,
来源：Acta Metallurgica Sinica(English Letters) 年份：2013
To study the effect of tungsten, vanadium and tantalum on the microstructures in CLAM (China Low Activation Martensitic) steel after irradiation respectively, t...
[会议论文] 作者：Pingping Liu,Wen Hu,Yumei Jia,Wentuo Han,Xiaoou Yi,Qian Zhan,Farong Wan,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
Beryllium is planned to be used as a neutron multiplier in the Helium-cooled ceramic breeder(HCCB)test blanket module(TBM)which is the primary option of the Chinese TBM program.The character of the mi...
[会议论文] 作者：Wen Hu,Pingping Liu,Yumei Jia,Wentuo Han,Xiaoou Yi,Qian Zhan,Farong Wan,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
Beryllium metal is a promising neutron multiplier materials for tritium-breeding blanket of a fusion reactor.However,some problems are anticipated for the application of beryllium in DEMO blanket that...
[会议论文] 作者：Xiaoou Yi,Duc Nguyen-Mahn,Kazuto Arakawa,Francesco Ferroni,Pingping Liu,Wentuo Han,Farong Wan,Steven,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
Tungsten-based materials form a prime candidate of plasma facing components in fusion power reactors,and are subject to substantial amount of radiation damage from the bombardments of fast neutrons,as...
[会议论文] 作者：Lei Zhang,Lijuan Cui,Jin Gao,Yufeng Du,Gaowei Zhang,Shanwu Yang,Qian Zhan,Yi Long,Farong Wan,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
Vanadium alloys are considered as candidate materials for structure application in fusion reactors because of their low radiation-induced activation,high resistance to radiation damage,high thermal co...
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