Paper Titles

A Comparative Study on the Friction and Wear Properties of Three Different Copper Alloys
p.205

Experimental Study and Numerical Simulation of Microstructure Evolution in Al-Si Eutectic Solidification Process
p.212

Influence of Silicon on Nucleation and Growth Process of Spherical Graphite in Ni-C Alloys Solidification Structure
p.220

Effects of Process Parameters on Morphologies and Microstructures of Laser Melting Deposited V-5Cr-5Ti Alloys
p.227

Rate Theory for Dislocation Loops Evolution in AL-6XN Austenitic Stainless Steel under Proton Irradiation
p.237

Fatigue Mechanism of Domestic 316LN Stainless Steel in Simulated AP1000 First-Loop Water Environment
p.247

Influence of Warm Deformation on Strain-Induced Martensite Behavior of 316L Stainless Steel
p.254

Formation of Face Centered Cubic Titanium Thin Films on MgO(111) Single Crystal Substrate
p.264

Effect of Annealing Temperature on Microstructure and Properties of Ultra Purified Ferritic Stainless Steel Containing Copper
p.270

HomeMaterials Science ForumMaterials Science Forum Vol. 913Rate Theory for Dislocation Loops Evolution in...

Rate Theory for Dislocation Loops Evolution in AL-6XN Austenitic Stainless Steel under Proton Irradiation

Article Preview

Abstract:

The average size and density evolution of dislocation loops in AL-6XN austenitic stainless steel, a candidate fuel cladding material for supercritical water-cooled reactor, under proton irradiation were simulated through a rate theory model. The simulation results exhibit relatively good agreement with the experimental results at 563 K. The size and density of defect clusters are calculated under irradiation temperature between 550 K and 900 K and irradiation doses up to 15 dpa which satisfies the working condition in supercritical water-cooled reactor. The fast nucleation between self-interstitials happens at the initial stage of irradiation. The average size of dislocation loops increases while the average density of these loops reduces with the increasing temperature, and the average density approaches to a constant when irradiated at higher irradiation doses. The mechanism is discussed based on the variation of rate constants of defect reactions and the variation of the diffusion coefficients of interstitials and dislocation loops with dose and temperature.

You might also be interested in these eBooks

Functional and Functionally Structured Materials II

Info:

Periodical:

Materials Science Forum (Volume 913)

Pages:

237-246

DOI:

https://doi.org/10.4028/www.scientific.net/MSF.913.237

Citation:

Cite this paper

Online since:

February 2018

Authors:

Yan Xia Yu*, Li Ping Guo, Zheng Yu Shen, Yun Xiang Long, Zhong Cheng Zheng, Rui Tang

Keywords:

AL-6XN, Dislocation Loops, Proton Irradiation, Rate Theory

Export:

RIS, BibTeX

Price:

Permissions CCC:

Request Permissions

Permissions PLS:

Request Permissions

Сopyright:

© 2018 Trans Tech Publications Ltd. All Rights Reserved

Share:

Citation:

* - Corresponding Author

[1] C. Sun, R. Hui, W. Qu, S. Yick, Progress in corrosion resistant materials for supercritical water reactors. Corros. Sci. 51 (2009) 2508-2523.

DOI: 10.1016/j.corsci.2009.07.007

[2] G.S. Was, P. Ampornrat, G. Gupta, S. Teysseyre, E.A. West, T.R. Allen, K. Sridharan, L. Tan, Y. Chen, X. Ren, C. Pister, Corrosion and stress corrosion cracking in supercritical water. J. Nucl. Mater. 371 (2007) 176-201.

DOI: 10.1016/j.jnucmat.2007.05.017

[3] M. Naidin, S. Mokry, F. Baig, Y. Gospodinov, U. Zirn, I. Pioro, G. Naterer, Thermal-Design Options for Pressure-Channel SCWRS With Cogeneration of Hydrogen. J. Eng. Gas. Turb. Power, 131 (2009) 012901.

DOI: 10.1115/1.2983016

[4] S. Baindur, Materials challenges for the supercritical water-cooled reactor (SCWR). Bullet. Canad. Nucl. Soci, 29 (2008) 32-38.

[5] J. Buongiorno, P. MacDonald, Supercritical water reactor (SCWR). Progress Report for the FY-03 Generation-IV R&D Activities for the Development of the SCWR in the US, INEEL/Ext-03-03-01210, INEEL, USA, September, (2003).

[6] S. Nemat-Nasser, W. -G. Guo, D.P. Kihl, Thermomechanical response of AL-6XN stainless steel over a wide range of strain rates and temperatures. J Mech. Phys. Solids, 49 (2001) 1823-1846.

DOI: 10.1016/s0022-5096(00)00069-7

[7] A.J. Sedriks, Corrosion of stainless steel, 2 (1996).

[8] F. Abed, G. Voyiadjis, Plastic deformation modeling of AL-6XN stainless steel at low and high strain rates and temperatures using a combination of bcc and fcc mechanisms of metals. Int. J Plasticity, 21 (2005) 1618-1639.

DOI: 10.1016/j.ijplas.2004.11.003

[9] B. Metrovich, Fatigue strength of welded AL-6XN superaustenitic stainless steel. Int. J Fatigue, 25(9-11) (2003) 1309-1315.

DOI: 10.1016/s0142-1123(03)00123-3

[10] M. Qian, J.N. DuPont, Microsegregation-related pitting corrosion characteristics of AL-6XN superaustenitic stainless steel laser welds. Corros. Sci. 52 (2010) 3548-3553.

DOI: 10.1016/j.corsci.2010.07.007

[11] S. Kalnaus, Y. Jiang, Fatigue of AL6XN stainless steel. J Eng. Mater. Tech. 130 (2008) 031013.

[12] R. Andreani, E. Diegele, R. Laesser, B. van der Schaaf, The European integrated materials and technology programme in fusion. J. Nucl. Mater. 329-333 (2004) 20-30.

DOI: 10.1016/j.jnucmat.2004.04.339

[13] M. Miyamoto, K. Ono, K. Arakawa, R.C. Birtcher, Effects of cascade damages on the dynamical behavior of helium bubbles in Cu. J. Nucl. Mater. 367-370 (2007) 350-354.

DOI: 10.1016/j.jnucmat.2007.03.129

[14] E.E. Bloom, S.J. Zinkle, F.W. Wiffen, Materials to deliver the promise of fusion power – progress and challenges. J. Nucl. Mater. 329-333 (2004) 12-19.

DOI: 10.1016/j.jnucmat.2004.04.141

[15] K. Forsberg, A.R. Massih, Kinetics of fission product gas release during grain growth. Model. Simul. Mater. Sc. 15 (2007) 335-353.

DOI: 10.1088/0965-0393/15/3/011

[16] C. Windsor, G. Cottrell, R. Kemp, A framework for predicting the yield stress, Charpy toughness and one hundred-year activation level for irradiated fusion power plant alloys. Model. Simul. Mater. Sc. 19 (2011) 035005.

DOI: 10.1088/0965-0393/19/3/035005

[17] A.L. Dunn, Simulating radiation damage accumulation in α-Fe: A spatially resolved stochastic cluster dynamics approach. Compu. Mater. Sci. 102 (2015) 13.

[18] Q. Xu, N. Yoshida, T. Yoshiie, Accumulation of helium in tungsten irradiated by helium and neutrons. J. Nucl. Mater. 367-370 (2007) 806-811.

DOI: 10.1016/j.jnucmat.2007.03.078

[19] S.G.N.M. Sharafat, Comparison of a microstructure evolution model with experiments on irradiated vanadium. J. Nucl. Mater. 283(Part 2) (2000) 5.

[20] E. Meslin, A. Barbu, L. Boulanger, B. Radiguet, P. Pareige, K. Arakawa, C.C. Fu, Cluster-dynamics modelling of defects in α-iron under cascade damage conditions. J. Nucl. Mater. 382 (2008) 190-196.

DOI: 10.1016/j.jnucmat.2008.08.010

[21] D. Xu, B.D. Wirth, Modeling spatially dependent kinetics of helium desorption in BCC iron following He ion implantation. J. Nucl. Mater. 403 (2010) 184-190.

DOI: 10.1016/j.jnucmat.2010.06.025

[22] K. Arakawa, K. Ono, M. Isshiki, K. Mimura, M. Uchikoshi, H. Mori, Observation of the one-dimensional diffusion of nanometer-sized dislocation loops. Science, 318(5852) (2007) 956-959.

DOI: 10.1126/science.1145386

[23] M. Kiritani, Defect interaction processes controlling the accumulation of defects produced by high energy recoils. J. Nucl. Mater. 251 (1997) 15.

DOI: 10.1016/s0022-3115(97)00278-x

[24] K. Arakawa, M. Hatanaka, E. Kuramoto, K. Ono, H. Mori, Changes in the Burgers Vector of Perfect Dislocation Loops without Contact with the External Dislocations. Phys. Rev. Lett. 96 (2006) 125506.

DOI: 10.1103/physrevlett.96.125506

[25] J. Gan, G. Was, R. Stoller, Modeling of microstructure evolution in austenitic stainless steels irradiated under light water reactor condition. J. Nucl. Mater. 299 (2001) 53-67.

DOI: 10.1016/s0022-3115(01)00673-0

[26] R.E. Stoller, G.R. Odette, A composite model of microstructural evolution in austenitic stainless steel under fast neutron irradiation; proceedings of the Radiation-Induced Changes in Microstructure, 13th International Symposium, ASTM STP, F, (1987).

DOI: 10.1520/stp33831s

[27] C. Pokor, Y. Brechet, P. Dubuisson, J. -P. Massoud, A. Barbu, Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part I: Evolution of the microstructure. J. Nucl. Mater. 326 (2004) 19-29.

DOI: 10.1016/j.jnucmat.2003.11.007

[28] T. Yoshiie, Q. Xu, K. Sato, K. Kikuchi, M. Kawai, Reaction kinetics analysis of damage evolution in accelerator driven system beam windows. J. Nucl. Mater. 377 (2008) 132-5.

DOI: 10.1016/j.jnucmat.2008.02.059

[29] D. Terentyev, I. Martin-Bragado, Evolution of dislocation loops in iron under irradiation: The impact of carbon. Scripta Mater. 97 (2015) 5-8.

DOI: 10.1016/j.scriptamat.2014.10.021

[30] G.S. Was, Fundamentals of radiation materials science: metals and alloys. Springer Science & Business Media, (2007).

[31] Y. Katoh, T. Muroga, A. Kohyama, R.E. Stoller, C. Namba, Rate theory modeling of defect evolution under cascade damage conditions: the influence of vacancy-type cascade remnants on defect evolution. J. Nucl. Mater. 233 (1996) 1022-1028.

DOI: 10.1016/s0022-3115(96)00088-8

[32] C. Dimitrov, O. Dimitrov, Composition dependence of defect properties in electron-irradiated Fe-Cr-Ni solid solutions. J Phys. F: Metal Phys. 14 (1984) 793.

DOI: 10.1088/0305-4608/14/4/005

[33] Y. Katoh, R.E. Stoller, Y. Kohno, A. Kohyama, The influence of He/dpa ratio and displacement rate on microstructural evolution: a comparison of theory and experiment. J. Nucl. Mater. 210 (1994) 290-302.

DOI: 10.1016/0022-3115(94)90183-x

[34] Y. Katoh, A. Kohyama, A computational study of defects evolution during irradiation in single-phase austenitic alloys. Materials Transactions, JIM, 34 (1993) 999-1005.

DOI: 10.2320/matertrans1989.34.999

[35] F. Christien, A. Barbu, Modelling of copper precipitation in iron during thermal aging and irradiation. J. Nucl. Mater. 324 (2004) 90-96.

DOI: 10.1016/j.jnucmat.2003.08.035

[36] A.H. Duparc, C. Moingeon, N. Smetniansky-de-Grande, A. Barbu, Microstructure modelling of ferritic alloys under high flux 1 MeV electron irradiations. J. Nucl. Mater. 302 (2002) 143-155.

DOI: 10.1016/s0022-3115(02)00776-6

[37] W. Phythian, R. Stoller, A. Foreman, A. Calder, D. Bacon, A comparison of displacement cascades in copper and iron by molecular dynamics and its application to microstructural evolution. J. Nucl. Mater. 22 (1995) 245-261.

DOI: 10.1016/0022-3115(95)00022-4

[38] Y. Naoaki, Evolution of microstructure in Fe-Cr-Ni austenitic alloys during irradiation. J. Nucl. Mater. 205 (1993) 344-353.

DOI: 10.1016/0022-3115(93)90099-k

[39] M. Caturla, N. Soneda, E. Alonso, B. Wirth, T.D. de la Rubia, J. Perlado, Comparative study of radiation damage accumulation in Cu and Fe. J. Nucl. Mater. 276 (2000) 13-21.

DOI: 10.1016/s0022-3115(99)00220-2

[40] H. Trinkaus, B. Singh, A. Foreman, Impact of glissile interstitial loop production in cascades on defect accumulation in the transient. J. Nucl. Mater. 206 (1993) 200-211.

DOI: 10.1016/0022-3115(93)90124-h