Development of Tubing Technique for High-Purity Low Activation Vanadium Alloys

Nagasaka, Tetsuya; Muroga, T.; Iikubo, Tomohito

doi:10.13182/fst03-a379

Cited by 21 publications

(18 citation statements)

References 6 publications

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“…NIFS has been mainly developing high purity vanadium alloy (V-4Cr-4Ti), NIFS-HEAT, for a long time in collaboration with many universities. The high machinability and weldability of NIFS-HEAT were demonstrated till 2003 [43], whereas the applicability to the blanket has been investigated through various experiments such as neutron exposure. Also the applicability of NIFS-HEAT coated by tungsten to the first wall has been investigated.…”

Section: Simulation Science Projectmentioning

confidence: 99%

Recent Fusion Research in the National Institute for Fusion Science

Komori

Sakakibara

Sagara

et al. 2011

Plasma and Fusion Research

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The National Institute for Fusion Science (NIFS), which was established in 1989, promotes academic approaches toward the exploration of fusion science for steady-state helical reactor and realizes the establishment of a comprehensive understanding of toroidal plasmas as an inter-university research organization and a key center of worldwide fusion research. The Large Helical Device (LHD) Project, the Numerical Simulation Science Project, and the Fusion Engineering Project are organized for early realization of net current free fusion reactor, and their recent activities are described in this paper. The LHD has been producing high-performance plasmas comparable to those of large tokamaks, and several new findings with regard to plasma physics have been obtained. The numerical simulation science project contributes understanding and systemization of the physical mechanisms of plasma confinement in fusion plasmas and explores complexity science of a plasma for realization of the numerical test reactor. In the fusion engineering project, the design of the helical fusion reactor has progressed based on the development of superconducting coils, the blanket, fusion materials and tritium handling.

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Section: Simulation Science Projectmentioning

confidence: 99%

Recent Fusion Research in the National Institute for Fusion Science

Komori

Sakakibara

Sagara

et al. 2011

Plasma and Fusion Research

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“…A limited quantity of creep tubing was prepared in Japan from the NIFS-HEAT-2 material using a three-directional rolling process [5] and the problems encountered with surface cracking and interstitial pick-up were less severe than those experienced with Batch A of the US heat.…”

Section: Processing Conditions For Batches a And Bmentioning

confidence: 99%

“…In an attempt to reduce the rate of oxygen pickup and to eliminate the surface cracking which occurred in Batch A, several changes were made in the drawing and annealing procedure; these changes in part benefited from the experience gained with the NIFS heat [5]. The cleaning procedure to remove the die lubricant was revised and problems associated with the bonding of the Ti wrap to the tubing surface during Batch A annealing were eliminated by using a tent consisting of multiple layers of clean Ta foil.…”

Section: Processing Conditions For Batches a And Bmentioning

confidence: 99%

Oxidation behavior of a V–4Cr–4Ti alloy during the commercial processing of thin-wall tubing

Rowcliffe

Hoelzer

Kurtz

et al. 2007

Journal of Nuclear Materials

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“…Thin pipes, including those for pressurized creep tube specimens, were also successfully fabricated maintaining the impurity level, fine grain size and straight band precipitate distribution by maintaining a constant reduction ratio between the intermediate heat treatments. 19) Through the efforts for fabricating the creep tubes including plugging of end caps, the fine-scale EB welding technology was enhanced. 20) Joining of V-4Cr-4Ti by Gus Tungsten Arc (GTA) 21) and laser welding 22) methods was demonstrated.…”

Section: Fabrication Technologymentioning

confidence: 99%

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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Development of Tubing Technique for High-Purity Low Activation Vanadium Alloys

Cited by 21 publications

References 6 publications

Recent Fusion Research in the National Institute for Fusion Science

Recent Fusion Research in the National Institute for Fusion Science

Oxidation behavior of a V–4Cr–4Ti alloy during the commercial processing of thin-wall tubing

Vanadium Alloys for Fusion Blanket Applications

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