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A.K. Dureja
Researcher at Bhabha Atomic Research Centre
Publications - 5
Citations - 34
A.K. Dureja is an academic researcher from Bhabha Atomic Research Centre. The author has contributed to research in topics: Coolant & Ultimate tensile strength. The author has an hindex of 3, co-authored 5 publications receiving 26 citations.
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Journal ArticleDOI
Flow behaviour of autoclaved, 20% cold worked, Zr–2.5Nb alloy pressure tube material in the temperature range of room temperature to 800 °C
A.K. Dureja,Sucharita Sinha,Ankit Srivastava,R.K. Sinha,J.K. Chakravartty,P. Seshu,D.N. Pawaskar +6 more
TL;DR: In this paper, the authors used tensile tests carried out in the temperature range from room temperature to 800 °C using the samples taken out from a single pressure tube have been used to develop correlations for characterizing the strength parameters' variation as a function of axial location along length of the tube and the test temperature.
Journal ArticleDOI
Modelling flow and work hardening behaviour of cold worked Zr–2.5Nb pressure tube material in the temperature range of 30–600 ̊C
TL;DR: In this paper, the tensile flow and work-hardening behavior of a cold worked Zr-2.5Nb pressure tube material of IPHWRs has been studied over the temperature range of 30-600 C. The results have been discussed in terms of the correlation coefficient and in error in the estimation of UTS and uniform strain.
Journal ArticleDOI
Experimental determination of thermal contact conductance between pressure and calandria tubes of Indian pressurised heavy water reactors
TL;DR: In this article, the authors measured thermal contact conductance between pressure tube and calandria tube specimens under axial contact pressure in between mandrels and reported a linear correlation as a function of contact pressure.
Thermo-mechanical Behaviour of Coolant Channels for Heavy Water Reactors under Accident Conditions
TL;DR: In this article, the deformation characteristics of the pressure tube have been modeled using finite element based program and the role of nonlinear stress-strain laws in the finite element analyses.
Journal ArticleDOI
Analysis of Interaction of Calandria Tubes with the End Shields in Advanced Heavy Water Reactor (AHWR)
TL;DR: In this article, a Calandria tube of annealed Zircaloy-4 alloy is attached at its ends to the side tube-sheets of both the bottom and top end shields.