Overview of materials research for fusion reactors

Muroga, T.; Gasparotto, M.; Zinkle, S.J.

doi:10.1016/s0920-3796(02)00219-3

Cited by 213 publications

(97 citation statements)

References 27 publications

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“…49) As the reference materials, Reduced Activation Ferritic/Martensitic Steels (RAFMs) were selected because they have the most matured industrial infrastructure. Development of the reference materials is crucial for realization of DEMO in timely manner.…”

Section: Strategy Of Vanadium Alloy Development For Fusion Blanketmentioning

confidence: 99%

“…This strategy is common to that of EU. 49,50) For the qualification of materials up to the full lifetime of DEMO and Power Plant Reactors, irradiation testing with IFMIF (International Fusion Materials Irradiation Test Facility, a 14 MeV neutron source) is recognized to be essential.…”

Section: Strategy Of Vanadium Alloy Development For Fusion Blanketmentioning

confidence: 99%

“…52) Figure 6 shows the roadmap of vanadium alloy development. This is arranged from the road map shown before 49) for showing exclusively for vanadium alloys. The materials development is planned to proceed with IFMIF and ITER in a coordinated way.…”

Section: Strategy Of Vanadium Alloy Development For Fusion Blanketmentioning

confidence: 99%

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Vanadium Alloys for Fusion Blanket Applications

Muroga

2005

Mater. Trans.

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Vanadium alloys are attractive candidate structural materials for breeding blanket of fusion reactors because of their low activation properties and high temperature strength. Studies on various blanket designs are being carried out using vanadium alloys as structural materials and liquid lithium or molten salt Flibe as breeding and coolant materials. Recently significant progress in fabrication technology has been made for vanadium alloys through a program of producing large ingots of high purity V-4Cr-4Ti (NIFS-HEATs). Fundamental understandings on the effects of interstitial impurities (C, N, O) on mechanical properties, radiation effects on microstructure and mechanical properties, corrosion and compatibility in various environments were enhanced. New promising candidates were identified for the MHD insulator coating. Among the remaining critical issues are the effects of transmutant helium on mechanical properties and development of long life MHD coating. Development of vanadium alloys will be carried out in coordination with IFMIF and ITER-TBM schedules as essential tools for verification of their performance in fusion blanket environments.

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Section: Strategy Of Vanadium Alloy Development For Fusion Blanketmentioning

confidence: 99%

Section: Strategy Of Vanadium Alloy Development For Fusion Blanketmentioning

confidence: 99%

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Vanadium Alloys for Fusion Blanket Applications

Muroga

2005

Mater. Trans.

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“…A good example is selecting and designing fusion materials. The nuclear-fusion community has made significant effort to develop and characterize reduced-activation ferritic/martensitic steels (RAFM) [7,8]. The goal is to design ferritic/martensitic materials that have specific physical properties (high-temperature strength, radiation tolerance) and exhibit as little as possible activation and transmutation of alloying elements into radioactive isotopes because these effects make maintenance of a fusion plant difficult and increase the amount of radioactive waste that must be stored.…”

Section: Introduction: Accelerating Nuclear Design By Expanding Tradimentioning

confidence: 99%

Materials selection for nuclear applications: Challenges and opportunities

et al. 2018

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a b s t r a c t a r t i c l e i n f oWe discuss the challenge of selecting materials for nuclear applications and outline the need for comprehensive databases to assist scientists and engineers in choosing materials that meet interdependent physical, chemical, and nuclear criteria. In conventional engineering, chemical and physical properties and the electronic structure of materials are typically the primary considerations; nuclear applications must also consider the nuclear physics characteristics of a material. Development of databases that correlate physical, chemical, and nuclear properties would accelerate and facilitate innovations in nuclear design.

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“…Currently, reduced activation ferritic/martensitic (RAFM) steels are considered as the primary candidates for blanket structural materials because of their most matured industrial infrastructure and relatively good irradiation resistance [1].…”

Section: Introductionmentioning

confidence: 99%

Long-Term Thermal Stability of Reduced Activation Ferritic/Martensitic Steels as Structural Materials of Fusion Blanket

Nagasaka

Muroga

2010

Plasma and Fusion Research

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In this work, the effects of thermal ageing on mechanical properties of JLF-1 and CLAM steels have been studied at temperatures in a range of 823-973 K. The results showed that the hardness increased slightly and the creep properties improved after ageing at 823 K for 2000 h for the both steels. On the other hand, the hardness decreased after ageing above 823 K, especially at 973 K for 100 h, and the creep property degraded at 973 K for 100 h. The Larson-Miller parameter was used for predicting the long-term creep performance based on the shortterm experiments at higher temperature with higher stress including the pre-ageing effects. By extrapolation to the typical blanket condition, 823 K for 100 000 h, the rupture stress was estimated to be about 140 MPa for the both steels. The present thermal ageing treatments influence the estimated rupture stress for about ±10 MPa for both steels.

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Overview of materials research for fusion reactors

Cited by 213 publications

References 27 publications

Vanadium Alloys for Fusion Blanket Applications

Vanadium Alloys for Fusion Blanket Applications

Materials selection for nuclear applications: Challenges and opportunities

Long-Term Thermal Stability of Reduced Activation Ferritic/Martensitic Steels as Structural Materials of Fusion Blanket

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