Title: Design and development of high-temperature tribometer for material testing in liquid sodium environment

Authors: Hemant Kumar; S. Vijayaraghavan; Shaju K. Albert; A.K. Bhaduri; K.K. Ray

Addresses: Department of Metallurgy & Materials Engineering, Indian Institute of Technology, Kharagpur, West Bengal 721302, India ' Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu 603102, India ' Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu 603102, India ' Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu 603102, India ' Department of Metallurgy & Materials Engineering, Indian Institute of Technology, Kharagpur, West Bengal 721302, India

Abstract: It is well known that high friction coefficients due to stripping of oxide films, wear and galling are common to many mating surfaces of the components of sodium cooled Fast Breeder Reactors (FBRs). Therefore, understanding tribological behaviour of various materials in liquid sodium is an important input for design of reactor components. In order to generate this information, a first-of-the-kind high-temperature Pin-on-Disc Tribometer (PODT) has been designed and fabricated for carrying out in-sodium sliding friction and wear studies in conditions simulating reactor operating conditions. The design of the tribometer incorporated consideration for convenience of operation in liquid sodium environment. The PODT system has been designed for the maximum temperature of 873 K and contact stress of 55 MPa; these parameters cover the temperature and stress levels prevailing in the operation of Indian FBRs. The appropriateness of the designed tribometer has been demonstrated with some typical experimental results.

Keywords: fast breeder reactors; FBR; pin-on-disc tribometers; sliding friction; sliding wear; galling; high temperature; liquid sodium; tribometer design; materials testing; nuclear reactors; nuclear energy; nuclear power; tribology; simulation; contact stress; India.

DOI: 10.1504/IJNEST.2016.078962

International Journal of Nuclear Energy Science and Technology, 2016 Vol.10 No.3, pp.276 - 285

Received: 03 May 2016
Accepted: 20 Jul 2016
Published online: 06 Sep 2016 *

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