Compatibility of Stainless Steel 316L with Lead-17 at.% Lithium with Reference to Indian-TBM

Chakraborty, Prateeti; Das, Chintamani; Kumar, Sanjay; Fotedar, R.K.

doi:10.1007/s12666-012-0153-6

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“…Corrosion of P91 in Pb-17Li has been analysed under static conditions and a suitable corrosion rate has been established. Corrosion of SS316L in Pb-17Li in the presence of various alloying elements like Nickel and Aluminum, have been studied up to 3200 h of exposure (Chakraborty et al 2012(Chakraborty et al , 2013. Interaction of Silicon Carbide with static Pb-17Li is also being investigated at a temperature of 823 K. SiC will be used in the making of electrically insulating flow inserts along the TBM coolant channel.…”

Section: Corrosion Testing Of Structural Materials In Lead Lithium Eumentioning

confidence: 99%

Material development for India’s nuclear power programme

Suri

2013

Sadhana

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The area of materials research has registered a phenomenal growth in the recent years, assiduously accepting and assimilating ideas, concepts and analytical as well as experimental methodologies and techniques form almost all scientific disciplines, thereby demonstrating its remarkably multidisciplinary and interdisciplinary character. The focus of the materials programme of this centre is to provide materials, processes and processing solutions to the emerging needs of evolving indigenous nuclear energy systems by proactive research and development on a continuing basis. The initial stage of our activities was formulated around three stage Indian nuclear power programme. In stage I, material issues related to in-core materials with emphasis on development of fabrication routes of zirconium alloys for structural application were addressed. Subsequently the thrust areas were development and characterization of mixed oxide fuel, advanced zirconium alloys, structural steels, superalloys, neutron absorber materials based on boron carbides and borides, and shape memory alloys. The research was useful for in-service performance evaluation, safety assessment, residual life estimation and life extension of nuclear reactors built during stage I i.e., PHWRs and BWRs. It also included developments which would permit rapid expansion of nuclear power initially through fast breeder reactor based on mixed oxide fuel and later based on metallic fuels. For the 3rd stage, multilayer coatings, graphite coolant tube, BeO, refractory metals and alloys, heat-treated zirconium alloys are being developed for CHTR, ADSS and AHWR. The materials being developed for fusion programme are low Z and high Z material for plasma facing application, Cu-alloys for heat sink, austenitic steels, RAFMS and ODS for structurals and NbTi, Nb 3 Sn and Nb 3 Al superconductors, lithium titanate, lithium silicate breeders, and Pb-Bi coolant. A brief overview of the materials research activities currently being pursued at Bhabha Atomic Research Centre is presented in this article.

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Section: Corrosion Testing Of Structural Materials In Lead Lithium Eumentioning

confidence: 99%

Material development for India’s nuclear power programme

Suri

2013

Sadhana

View full text Add to dashboard Cite

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Compatibility of Stainless Steel 316L with Lead-17 at.% Lithium with Reference to Indian-TBM

Cited by 1 publication

References 8 publications

Material development for India’s nuclear power programme

Material development for India’s nuclear power programme

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