References
- P. Yvon, M. Le Flem, C. Cabet, J.L. Seran, Structural materials for next generation nuclear systems: challenges and the path forward, Nucl. Eng. Des. 294 (2015) 161-169. https://doi.org/10.1016/j.nucengdes.2015.09.015
- S.J. Zinkle, J.T. Busby, Structural materials for fission & fusion energy, Mater. Today 12 (11) (2009) 12-19. https://doi.org/10.1016/S1369-7021(09)70294-9
- P. Yvon, F. Carre, Structural materials challenges for advanced reactor systems, J. Nucl. Mater. 385 (2) (2009) 217-222. https://doi.org/10.1016/j.jnucmat.2008.11.026
- A. Kostka, K. Tak, R. Hellmig, Y. Estrin, G. Eggeler, On the contribution of carbides and micrograin boundaries to the creep strength of tempered martensite ferritic steels, Acta Mater. 55 (2) (2007) 539-550. https://doi.org/10.1016/j.actamat.2006.08.046
- M. Nastar, F. Soisson, Radiation-induced segregation, Compr. Nucl. Mater. 1 (2012) 471-496.
- Y. Yang, K.G. Field, T.R. Allen, J.T. Busby, Roles of vacancy/interstitial diffusion and segregation in the microchemistry at grain boundaries of irradiated Fe-Cr-Ni alloys, J. Nucl. Mater. 473 (2016) 35-53. https://doi.org/10.1016/j.jnucmat.2016.02.007
- Z. Lu, R.G. Faulkner, G. Was, B.D. Wirth, Irradiation-induced grain boundary chromium microchemistry in high alloy ferritic steels, Scripta Mater. 58 (10) (2008) 878-881. https://doi.org/10.1016/j.scriptamat.2008.01.004
- J.P. Wharry, G.S. Was, A systematic study of radiation-induced segregation in ferritic-martensitic alloys, J. Nucl. Mater. 442 (1-3) (2013) 7-16. https://doi.org/10.1016/j.jnucmat.2013.07.071
- G.S. Was, J.P. Wharry, B. Frisbie, B.D. Wirth, D. Morgan, J.D. Tucker, T.R. Allen, Assessment of radiation-induced segregation mechanisms in austenitic and ferriticemartensitic alloys, J. Nucl. Mater. 411 (1-3) (2011) 41-50. https://doi.org/10.1016/j.jnucmat.2011.01.031
- K.G. Field, B.D. Miller, H.J.M. Chichester, K. Sridharan, T.R. Allen, Relationship between lath boundary structure and radiation induced segregation in a neutron irradiated 9wt.% Cr model ferritic/martensitic steel, J. Nucl. Mater. 445 (1-3) (2014) 143-148. https://doi.org/10.1016/j.jnucmat.2013.10.056
- R. Hu, G.D.W. Smith, E.A. Marquis, Effect of grain boundary orientation on radiation-induced segregation in a Fe-15.2at.% Cr alloy, Acta Mater. 61 (9) (2013) 3490-3498. https://doi.org/10.1016/j.actamat.2013.02.043
- K.G. Field, L.M. Barnard, C.M. Parish, J.T. Busby, D. Morgan, T.R. Allen, Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel, J. Nucl. Mater. 435 (1-3) (2013) 172-180. https://doi.org/10.1016/j.jnucmat.2012.12.026
- R.A. Johnson, N.Q. Lam, Solute segregation in metals under irradiation, Phys. Rev. B 13 (10) (1976) 4364-4375. https://doi.org/10.1103/PhysRevB.13.4364
- A.D. Marwick, Calculation of bias due to solute redistribution in an irradiated binary alloy: surfaces of a thin foil, J. Nucl. Mater. 135 (1) (1985) 68-76. https://doi.org/10.1016/0022-3115(85)90438-6
- R.C.P.A.D. Marwick, M.E. Horton, Radiation-induced Segregation in Fe-Cr-Ni Alloys, Dimensional Stability and Mechanical Behaviour of Irradiated Metals and Alloys, 1983.
- A.D. Marwick, Segregation in irradiated alloys : the inverse Kirkendall effect and the effect of constitution on void swelling, J. Phys. F Met. Phys. 8 (9) (1978) 1849-1861. https://doi.org/10.1088/0305-4608/8/9/008
- P.R. Okamoto, L.E. Rehn, Radiation-induced segregation in binary and ternary alloys, J. Nucl. Mater. 83 (1) (1979) 2-23. https://doi.org/10.1016/0022-3115(79)90587-7
- H. Wiedersich, P.R. Okamoto, N.Q. Lam, A theory of radiation-induced segregation in concentrated alloys, J. Nucl. Mater. 83 (1) (1979) 98-108. https://doi.org/10.1016/0022-3115(79)90596-8
- S.M. Murphy, Contribution of interstitial migration to segregation in concentrated alloys, J. Nucl. Mater. 182 (1991) 73-86. https://doi.org/10.1016/0022-3115(91)90416-5
- S.M. Murphy, J.M. Perks, Analysis of phosphorus segregation in ion-irradiated nickel, J. Nucl. Mater. 171 (2-3) (1990) 360-372. https://doi.org/10.1016/0022-3115(90)90382-W
- S.M. Murphy, A model for segregation in dilute alloys during irradiation, J. Nucl. Mater. 168 (1-2) (1989) 31-42. https://doi.org/10.1016/0022-3115(89)90561-8
- S.M.M.J.M. Perks, Modelling the Major Element Radiation-Induced Segregation in Concentrated Fe-Cr-Ni Alloys, Materials for Nuclear Reactor Core Applications, 1987.
- T.R. Allen, G.S. Was, Modeling radiation-induced segregation in austenitic Fe-Cr-Ni alloys, Acta Mater. 46 (10) (1998) 3679-3691. https://doi.org/10.1016/S1359-6454(98)00019-6
- T.R. Allen, J.T. Busby, G.S. Was, E.A. Kenik, On the mechanism of radiation-induced segregation in austenitic Fe-Cr-Ni alloys, J. Nucl. Mater. 255 (1) (1998) 44-58. https://doi.org/10.1016/S0022-3115(98)00010-5
- T.R. Allen, G.S. Was, E.A. Kenik, The effect of alloy composition on radiation-induced segregation in Fe Cr Ni alloys, J. Nucl. Mater. 244 (3) (1997) 278-294. https://doi.org/10.1016/S0022-3115(96)00744-1
- S. Watanabe, Y. Takamatsu, N. Sakaguchi, H. Takahashi, Sink effect of grain boundary on radiation-induced segregation in austenitic stainless steel, J. Nucl. Mater. 283-287 (2000) 152-156. https://doi.org/10.1016/S0022-3115(00)00204-X
- T.S. Duh, J.J. Kai, F.R. Chen, L.H. Wang, Numerical simulation modeling on the effects of grain boundary misorientation on radiation-induced solute segregation in 304 austenitic stainless steels, J. Nucl. Mater. 294 (3) (2001) 267-273. https://doi.org/10.1016/S0022-3115(01)00493-7
- K.G. Field, Y. Yang, T.R. Allen, J.T. Busby, Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments, Acta Mater. 89 (2015) 438-449. https://doi.org/10.1016/j.actamat.2015.01.064
- J.P. Wharry, G.S. Was, The mechanism of radiation-induced segregation in ferritic-martensitic alloys, Acta Mater. 65 (2014) 42-55. https://doi.org/10.1016/j.actamat.2013.09.049
- G.S. Was, Fundamentals of Radiation Materials Science Metals and Alloys, 2007.
- L.D. Xia, W.B. Liu, H.P. Liu, J.H. Zhang, H. Chen, Z.G. Yang, C. Zhang, Radiation damage in helium ion-irradiated reduced activation ferritic/martensitic steel, Nucl. Eng. Technol. 50 (1) (2018) 132-139. https://doi.org/10.1016/j.net.2017.10.012
- P. Lejcek, Grain Boundary Segregation in Metals, 2010.
- Y.N. Osetsky, A. Serra, Vacancy and interstitial diffusion in bcc-Fe, Defect Diffusion Forum 143 (1997) 155-160. https://doi.org/10.4028/www.scientific.net/ddf.143-147.155
- S.J. Rothman, L.J. Nowicki, G.E. Murch, Self-diffusion in austenitic Fe-Cr-Ni alloys, J. Phys. F Met. Phys. 10 (3) (1980) 383-398. https://doi.org/10.1088/0305-4608/10/3/009
- J.P. Wharry, Z. Jiao, G.S. Was, Application of the inverse Kirkendall model of radiation-induced segregation to ferritic-martensitic alloys, J. Nucl. Mater. 425 (1-3) (2012) 117-124. https://doi.org/10.1016/j.jnucmat.2011.10.035
- D.G. Brandon, The structure of high-angle grain boundaries, Acta Metall. 14 (11) (1966) 1479-1484. https://doi.org/10.1016/0001-6160(66)90168-4
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