Effect of helium implantation on mechanical properties and microstructure evolution of reduced-activation 9Cr–2W martensitic steel

Kasada, Ryuta; Morimura, Toshiya; Hasegawa, Akira; Kimura, Akihiko

doi:10.1016/s0022-3115(01)00660-2

Cited by 24 publications

(20 citation statements)

References 22 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Although helium might cause further degradation, no difference was observed in the relationship of Á y -ÁDBTT between fast neutron irradiation and He ion implantation, as shown in Fig. 4, 6,38) indicating that the observed embrittlement is interpreted in terms of hardeningmechanism in both cases. Previous works on helium effects are introduced as follows.…”

Section: Effects Of Helium On Irradiation Embrittlementmentioning

confidence: 86%

“…13,14,38) Homogeneous implantation with helium by using an energy degrader at a temperature below 423 K resulted in a shift in SP-DBTT. The shift becomes larger with increasing helium or displacement damage.…”

Section: Effects Of Helium Implantationmentioning

confidence: 99%

“…37) It is of notice that the relation between Á y -ÁDBTT of a RAF/M steel implanted with 580 appm of helium is almost same with that of the steels without helium. 38) This suggests that the ÁDBTT of helium-implanted steel is reasonably interpreted in terms of not helium embrittlement but displacement damage-induced embrittlement where helium implantation simply plays a role of atomic displacement. Helium issues will be discussed in section 2.2.…”

mentioning

confidence: 99%

See 2 more Smart Citations

Current Status of Reduced-Activation Ferritic/Martensitic Steels R&D for Fusion Energy

Kimura

2005

Mater. Trans.

View full text Add to dashboard Cite

Reduced-activation ferritic/martensitic (RAF/M) steels have been considered to be the prime candidate for the fusion blanket structural material. The irradiation data obtained up to now indicates rather high feasibility of the steels for application to fusion reactors because of their high resistance to degradation of material performance caused by both the irradiation-induced displacement damage and transmutation helium atoms. The martensitic structure of RAF/M steels consists of a large number of lattice defects before the irradiation, which strongly retards the formation of displacement damage through absorption and annihilation of the point defects generated by irradiation. Transmutation helium can be also trapped at those defects in the martensitic structure so that the growth of helium bubbles at grain boundaries is suppressed. The major properties of the steels are well within our knowledge, and processing technologies are mostly developed for fusion application. RAF/M steels are now certainly ready to proceed to the next stage, that is, the construction of International Thermo-nuclear Experimental Reactor Test Blanket Modules (ITER-TBM).Oxide dispersion strengthening (ODS) steels have been developed for higher thermal efficiency of fusion power plants. Recent irradiation experiments indicated that the steels were quite highly resistant to neutron irradiation embrittlement, showing hardening accompanied by no loss of ductility. High-Cr ODS steels whose chromium concentration was in the range from 14 to 19 mass% showed high resistance to corrosion in supercritical pressurized water. It is shown that the 14Cr-ODS steel is susceptible to neither hydrogen nor helium embrittlement.A combined utilization of ODS steels with RAF/M steels will be effective to realize fusion power early at a reasonable thermal efficiency.

show abstract

Section: Effects Of Helium On Irradiation Embrittlementmentioning

confidence: 86%

Section: Effects Of Helium Implantationmentioning

confidence: 99%

mentioning

confidence: 99%

See 1 more Smart Citation

Current Status of Reduced-Activation Ferritic/Martensitic Steels R&D for Fusion Energy

Kimura

2005

Mater. Trans.

View full text Add to dashboard Cite

show abstract

“…The embrittlement of RAFM EUROFER97 was studied by the implantation of hydrogen, in which yield stress as well as tensile strength increased and uniform as well as fracture strains decreased after hydrogen implantation [10]. Moreover, the effects of helium on the swelling activity, ductile to brittle transition temperature (DBTT) and irradiation hardening were investigated in a reduced activation martensitic steel [11]. The synergistic effects of helium and hydrogen were also investigated with dual or triple ion irradiation in several different kinds of steels, which had complex influences on the http://dx.doi.org/10.1016/j.fusengdes.2015.01.001 0920-3796/© 2015 Elsevier B.V. All rights reserved.…”

Section: Introductionmentioning

confidence: 99%

Helium and hydrogen irradiation induced hardening in CLAM steel

Liu

Wan

et al. 2015

Fusion Engineering and Design

View full text Add to dashboard Cite

“…In order to understand effects of the transmutation helium on irradiation embrittlement of the RAF steels and other ferritic steels, many efforts have been made by using various simulation methods, such as isotopic tailoring and helium ion implantation, for the helium generation in fusion environment. [1][2][3][4][5][6][7] However, it is very difficult to quantify heliumrelated embrittlement because these methods have shown some controversial results. Especially, Ni-isotope tailoring (NIT) method provided two different interpretations concerning whether a significant embrittlement observed for ferritic steels containing about 390 appm helium after neutron irradiation in the High Flux Isotope Reactor (HFIR) was due to helium or not.…”

Section: Introductionmentioning

confidence: 99%

Effects of Nickel Addition on Microstructural Evolution and Mechanical Properties of Reduced Activation Martensitic Steels Irradiated in the ATR-A1

Kasada

Kimura

2005

Mater. Trans.

View full text Add to dashboard Cite

Validity of nickel isotope tailoring (NIT) method to be able to generate a large amount of transmutation helium in 9%Cr-2%W reduced activation ferritic (RAF) steel for fusion reactor structural material was investigated and discussed through mechanical properties and microstructural evolution after fission neutron irradiation. Miniature tensile and Charpy impact specimens of RAF steels and 1% nickel added RAF steel were irradiated in the ATR-A1 to evaluate irradiation hardening and shift in ductile-brittle transition temperature (ÁDBTT). The amount of transmutation helium in all the RAF steels with and without nickel addition was calculated as only about 0.6 appm. After irradiation at 621 K, the ÁDBTT for the 1% nickel added steel was similar for the JLF-1. After irradiation at 543 K, however, the ÁDBTT for the 1% nickel added steel was significantly larger than that for the JLF-1. Microstructure observations revealed that irradiation-induced dislocation loops in the 1% nickel added steel were finer and denser than in the RAF steel without nickel addition, suggesting that the nickel addition to the RAF steels directly affected nucleation and growth processes of dislocation loops and enhanced irradiation hardening and embrittlement. Therefore, there is a limit in the NIT method as a simulation method for understanding effects of helium on irradiation embrittlement of RAF steels.

show abstract

Effect of helium implantation on mechanical properties and microstructure evolution of reduced-activation 9Cr–2W martensitic steel

Cited by 24 publications

References 22 publications

Current Status of Reduced-Activation Ferritic/Martensitic Steels R&D for Fusion Energy

Current Status of Reduced-Activation Ferritic/Martensitic Steels R&D for Fusion Energy

Helium and hydrogen irradiation induced hardening in CLAM steel

Effects of Nickel Addition on Microstructural Evolution and Mechanical Properties of Reduced Activation Martensitic Steels Irradiated in the ATR-A1

Contact Info

Product

Resources

About