High temperature performance of highly purified V–4Cr–4Ti alloy, NIFS-Heat1

Fukumoto, Kazuhiro; Yamamoto, Takuya; Nakao, Nobuhiro; Takahashi, Shigeru; Matsui, Hideki

doi:10.1016/s0022-3115(02)01216-3

Cited by 20 publications

(22 citation statements)

References 19 publications

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“…These data demonstrate that Cr significantly increases the creep resistance of V. More recently, several studies have characterized the thermal creep performance of V-4Cr-4Ti in vacuum and liquid Li [37][38][39][40][41][42][43][44]. Both uniaxial [37,38] and biaxial [41,42] tests were performed in vacuum with different starting concentrations of interstitial O.…”

Section: Thermal and Irradiation Creepmentioning

confidence: 98%

“…This is consistent with the vacuum creep data since Li has a higher affinity for O than V and will, after long exposure times, lower the O level in the alloy. Recently Fukumoto et al [38] and Koyama et al [44] utilized a novel Zr-foil gettering heat treatment to reduce interstitial O and N concentrations to very low levels in V-4Cr-4Ti and V-10Cr-5Ti sheet stock. Tensile specimens prepared from these highly purified alloys were used to study dynamic strain aging (DSA) and creep properties.…”

Section: Thermal and Irradiation Creepmentioning

confidence: 99%

See 1 more Smart Citation

Recent progress on development of vanadium alloys for fusion

Kurtz

Abe

Чернов

et al. 2004

Journal of Nuclear Materials

147

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Section: Thermal and Irradiation Creepmentioning

confidence: 98%

Section: Thermal and Irradiation Creepmentioning

confidence: 99%

Recent progress on development of vanadium alloys for fusion

Kurtz

Abe

Чернов

et al. 2004

Journal of Nuclear Materials

147

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“…Since thermal creep properties of NIFS-HEAT-2, containing C, O and N impurities of 100 massppm each, were shown to be similar to those of other V-4Cr-4Ti alloys having higher levels of the impurities, 26) reduction of the impurities to 100 massppm is thought not to induce loss of strength. However, significant increase in creep strain rate was reported recently in V-4Cr-4Ti with oxygen level of 10 massppm.…”

Section: Impurity Effectsmentioning

confidence: 97%

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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“…The upper temperature limit for vanadium alloys is assumed to be 700-750°C, and is most probably determined by compatibility with the fusion environment, the effect of gaseous transmutants such as helium, and mechanical properties such as tensile properties and creep resistance [3]. Thermal creep properties of V-4Cr-4Ti alloy have been investigated by uniaxial tensile and biaxial pressurized tube specimens [4][5][6]. The data base on irradiation creep is still very limited but has been accumulated gradually.…”

Section: Introductionmentioning

confidence: 99%