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References    185





                  REFERENCES
                   [1] Banerjee S, Chakravartty JK, Dubey JS, Singh RN, Srivastava D. Role of basic research
                      in the development of zirconium alloys for nuclear applications, In: De PK, editor. Proc.
                      international symposium on advances in zirconium, Mumbai, India; 2002. p. 40–55.
                   [2] Chow CK, Simpson LA. Determination of the fracture toughness of irradiated reactor
                      pressure tubes using curved compact specimen, In: Read DT, Reed R, editors. Proc.
                      18th symposium on fracture mechanics. ASTM STP 945; 1985. p. 419–39.
                   [3] Ganguly C. Advances in zirconium technology for nuclear reactor application,
                      In: De PK, editor. Proc. international symposium on advances in zirconium, Mumbai,
                      India; 2002. p. 1–27.
                   [4] Arsene S, Bai J. New approach to measure the transverse properties of structural tubing
                      by a ring test. ASTM J Test Eval 1996;24(6):386–91.
                   [5] Josefsson B, Grigoriev V. Modified ring tensile testing and a new method for fracture
                      toughness testing of irradiated cladding. Studsvik Material AB, S-61182, Nykoping,
                      Sweden; 1996.
                   [6] Seok CS, Bae BK, Koo JM, Murty KL. The properties of the ring and burst creep of
                      ZIRLO cladding. Eng Fail Anal 2006;13:389–97.
                   [7] Lee KW, Kim SK, Kim KT, Hong SI. Ductility and strain rate sensitivity of Zircaloy-4
                      nuclear fuel claddings. J Nucl Mater 2001;295:21–6.
                   [8] Leclercq S, Parrot A, Leroy M. Failure characteristics of cladding tubes under RIA con-
                      ditions. Nucl Eng Des 2008;238(9):2206–18.
                   [9] Chung H, Kassner T. Cladding metallurgy and fracture behavior during reactivity-
                      initiated accidents at high burn-up. Nucl Eng Des 1998;186:411–27.
                  [10] Samal MK, Balakrishnan KS, Parashar J, Tiwari GP, Anantharaman S. Estimation of ten-
                      sile behavior of zirconium alloy pressure tubes using ring tensile test and finite element
                      analysis. J Mech Eng Sci 2013;227(6):1177–86.
                  [11] Samal MK, Balakrishnan KS, Parashar J, Tiwari GP. Investigation of deformation behav-
                      iour of ring-tensile specimens machined from pressure tubes of Indian PHWR. Trans
                      Indian Inst Met 2014;67(2):167–76.
                  [12] Balakrishnan KS, Samal MK, Parashar J, Tiwari GP, Anantharaman S. Suitability of
                      miniature tensile specimens for estimating the mechanical property data of pressure
                      tubes—an assessment. Trans Indian Inst Met 2014;67(1):47–55.
                  [13] Samal MK, Balakrishnan KS, Balakrishnan S. A practical approach to evaluate stress-
                      strain behavior of remotely handled pressure tubes of nuclear reactors using ring tension
                      test. Trans Indian Inst Met 2014;68:299–310. http://dx.doi.org/10.1007/s12666-014-
                      0461-0.
                  [14] Grigoriev V, Josefsson A, Lind B, Rosborg A. Pin loading tension test for evaluation of
                      evaluation of thin walled tubular material. Scr Metall Mater 1995;33:109–14.
                  [15] Grigoriev V, Jakobsson R. Application of the Pin Loading Tension test to measurements
                      of delayed hydride cracking velocity in Zircaloy cladding. SKI Rapport 00:57, Studsvik
                      Nuclear AB, SE-611 82 Nyk€ oping, Sweden; 2000.
                  [16] Grigoriev V, Jakobsson R. Delayed hydrogen cracking velocity and j-integral measure-
                      ments on irradiated BWR cladding. J ASTM Int 2005;2(8):1–16.
                  [17] Sainte Catherine C, Le Boulch D, Carassou S, Ramasubramanian N, Lemaignan C. An
                      internal conical mandrel technique for fracture toughness measurement in nuclear fuel
                      cladding. ASTM J Test Eval 2006;35(5):373–82.
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