氘、氚与RAFM钢相容性研究进展

doi:10.11896/cldb.18090029

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Abstract Nuclear fusion achieved through deuterium and tritium is the most effective way to solve the energy crisis and environmental issues. The magnetic confinement fusion is currently the most promising steady-state research reactor. However, there are many challenges to be solved including materials design and development which is essential to the commercial application of fusion energy. The blanket structural materials are not only subjected to high heat load and severe corrosion in the service process, but also bombarded by various particles such as deuterium (D), tritium (T), helium (He) and high energy neutrons produced by D-T fusion reaction. Up to now there are primarily four kinds of candidate structural materials which are austenitic stainless steel, low activation ferrite/martensitic (RAFM) steel, vanadium alloy and SiC composites, respectively. RAFM steels have been proposed as the most promising candidate structural materials for the experimental fusion reactor ITER owing to their better swelling resistance, improved irradiation resistance and favorable termo-physical properties. It is fundamental to obtain the transport parameters of deuterium and tritium through RAFM steels for constructing the nuclear database. Although the transport behavior of deuterium in RAFM steels has been researched widely in recent years, the results obtained by different researc-hers are very different, and data on tritium are scared. Therefore, it is very necessary to establish the experimental test standard. RAFM steel has high deuterium and tritium permeability due to its lath martensitic structure, leading to fuel loss and tritium pollution. Thus direct contact between RAFM steel and hydrogen isotopes must be reduced or avoided. The preparation of tritium permeation barrier (TPB) on the surface of RAFM steel is one of the most effective ways to realize tritium self-sustainment. At present, Al₂O₃ coating has attracted much attention as typical candidate TPB materials for its self-healing capacity and low permeation reduction factor (PRF), in addition to the realization of engineering application. Moreover, the radiation damage and surface state change of RAFM steel during service will inevitably affect the transport behavior of deuterium and tritium. It is generally believed that the defects produced by irradiation will increase the retention of deuterium and tritium in metal materials. As a result of hydrogen accumulation, a degradation of mechanical performance like the structure strength and ductility would occur for the materials. Especially for tritium, when the He-3 produced by tritium decay reaches ppb level, helium embrittlement will be appeared. In addition to TPB, recent studies have focused on improving the hydrogen resistance and irradiation resistance of RAFM steel by controlling composition and improving heat treatment process. This article reviews the research progress of deuterium and tritium behaviors in RAFM steels. And the permeation and retention behaviors of deuterium and tritium in RAFM steels, as well as their effects on mechanical properties are presented respectively. The issues involved in the development of RAFM steel are analyzed and its prospect is looked forward. It is expected that this will offer reference for the database establishment of RAFM steel and the feasibility of serving in the fusion reactor.

Key words： deuterium (D) tritium (T) RAFM steel penetration mechanical properties

Published: 21 May 2019

CLC number:

TG142

Fund:This work was financially supported by the National Magnetic Confinement Fusion Programs (2015GB109006), the National Natural Science Foundation of China (51471154, 11775194).

About author:: Zhanlei Wang received his B.S. degree in material science and engineering from Hefei University of Technology in 2014. He is currently co-educating for his Ph.D. at Institute of Materials, China Academy of Engineering Physics under the supervision of Prof. Chang’an Chen and Prof. Kaigui Zhu. His research has focused on hydrogen isotopes compatibility issues on reduced activation ferritic/martensitic steels served as structure materials in a D-T fusion reactor.Chang’an Chen received his B.E. degree in environmental geochemistry from Zhejiang University in 1992 and received his Ph.D. degree in nuclear fuel cycle and materials from China Academy of Engineering Physics in 2003. Between 2012 and 2013,he was a visiting scientist at ITER organization in France where he assisted to complete the conceptual design of technical scheme for hot room and radioactive waste management in ITER. His main research interests focus on tritium fuel treatment process and new materials development.

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	WANG Zhanlei
	XIANG Xin
	YAN Jing
	GUO Yakun
	ZHU Kaigui
	CHEN Chang’an

Cite this article:

WANG Zhanlei,XIANG Xin,YAN Jing, et al. Research Progress of Deuterium and Tritium Compatibility Issues on Reduced Activation Ferritic/Martensitic Steel[J]. Materials Reports, 2019, 33(11): 1782-1786.

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http://www.mater-rep.com/EN/10.11896/cldb.18090029 OR http://www.mater-rep.com/EN/Y2019/V33/I11/1782

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