Journal Published Online: 11 July 2011
Volume 8, Issue 6

Microstructural Studies of Heat Treated Zr-2.5Nb Alloy for Pressure Tube Applications

CODEN: JAIOAD

Abstract

Zr-2.5Nb alloy is used as pressure tube material in pressurized heavy water reactors (PHWR). Generally, these pressure tubes are used in the cold drawn condition. Heat treated Zr-2.5Nb alloy pressure tubes are used in reaktor bolshoy moshchnosti kanalniy and FUGEN type of reactors. In recent times, there has been a greater interest toward increasing the life of pressure tubes in advanced reactors. In the present work, fabrication parameters were optimized to manufacture heat treated Zr-2.5Nb alloy tube. A quenching dilatometer study was performed to establish the continuous cooling transus temperature for the alloy used in this study. Heat treatment under controlled condition in a dilatometer was performed to study microstructure at different soaking temperatures and cooling rates. In the dilatometer, during gas quenching, quenching rates were varied from 0.06 to 100°C/s to assess the effect of cooling rate on resulting microstructures. Soaking temperature and cooling rates were varied to obtain martensitic microstructure with appropriate volume fractions of primary α. On the basis of the results obtained during controlled heat treatments performed in the quenching dilatometer, 883°C was selected as the soaking temperature and water as the quenching medium for the α + β quenching operation for large dimension tubes. The α + β quenched microstructures, consisting of fine martensite phase along with 20%–25% primary α volume fraction, were used for further cold deformation and subsequent aging below the recrystallization temperature. Aging at 540°C produced fully recovered and tempered structure consisting of βNb of equilibrium composition. Mechanical properties of the finished heat treated pressure tube (aged at 515°C/24 h) produced with the present route were similar to the cold work pressure tube. Tube produced with 540°C/24 h aging exhibited substantially higher yield strength value at reactor operating temperature (300°C). The bulk texture at different stages of fabrication was evaluated. The volume fraction of the primary α phase significantly controls the final texture.

Author Information

Saibaba, N.
Nuclear Fuel complex, India
Jha, S.
Nuclear Fuel complex, India
Tonpe, S.
Nuclear Fuel complex, India
Vaibhaw, Kumar
Nuclear Fuel complex, India
Deshmukh, V.
Nuclear Fuel complex, India
Ramana Rao, S.
Nuclear Fuel complex, India
Mani Krishna, K.
Materials Science Division, India
Neogy, S.
Materials Science Division, India
Srivastava, D.
Materials Science Division, India
Dey, G.
Materials Science Division, India
Kulkarni, R.
Post Irradiation and Examination Division, India
Rath, B.
Post Irradiation and Examination Division, India
Ramadasan, E.
Post Irradiation and Examination Division, India
Anantharaman, S.
Post Irradiation and Examination Division, India
Pages: 15
Price: $25.00
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Details
Stock #: JAI103213
ISSN: 1546-962X
DOI: 10.1520/JAI103213