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Philosophical Magazine Volume 85, 2005 - Issue 19
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Original Articles

Grain boundary impurity segregation and neutron irradiation effects in ferritic alloys

R. G. Faulkner Institute of Polymer Technology and Materials Engineering, Loughborough University, Loughborough, Leicestershire LE11 3TU, UK
,
R. B. Jones Baznutec Ltd, Yew Porch, Box, Stroud, Glos GL6 9HR, UK
,
Zheng Lu Institute of Polymer Technology and Materials Engineering, Loughborough University, Loughborough, Leicestershire LE11 3TU, UK
&
P. E. J. Flewitt * British Nuclear Fuels, British Nuclear Group, Berkeley Centre, Berkeley, Glos GL13 9PB, UK; Interface Analysis Centre, Bristol University, Bristol BS2 8BS, UK
Pages 2065-2099 | Received 18 Jun 2004, Accepted 29 Oct 2004, Published online: 21 Feb 2007

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Read on this site (3)

J. E. Zelenty. (2015) Understanding thermally induced embrittlement in low copper RPV steels utilising atom probe tomography. Materials Science and Technology 31:8, pages 981-988.
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D Duffy. (2011) Modelling materials for fusion power. International Materials Reviews 56:5-6, pages 324-340.
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M. R. Wootton, R. Moskovic, C. J. Bolton & P. E. J. Flewitt. (2008) Experience of surveillance schemes adopted for magnox steel reactor pressure vessels. Energy Materials 3:1, pages 45-56.
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Articles from other publishers (26)

L. Cui, Y. Dai, S. Gerstl, M. Pouchon, X. Huang, M. Willinger & R. Schaublin. (2020) Characterization of Grain Boundary Segregation in Ferritic/Martensitic Steel after Irradiation in SINQ Target 4. Characterization of Grain Boundary Segregation in Ferritic/Martensitic Steel after Irradiation in SINQ Target 4.
Guy O.H. Whillock, Brian J. Hands, Tom P. Majchrowski & David I. Hambley. (2018) Investigation of thermally sensitised stainless steels as analogues for spent AGR fuel cladding to test a corrosion inhibitor for intergranular stress corrosion cracking. Journal of Nuclear Materials 498, pages 187-198.
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GARY S. WASGary S. Was. 2017. Fundamentals of Radiation Materials Science. Fundamentals of Radiation Materials Science 255 299 .
Aida Amroussia, Mikhail Avilov, Carl J. Boehlert, Florent Durantel, Clara Grygiel, Wolfgang Mittig, Isabelle Monnet & Frederique Pellemoine. (2015) Swift heavy ion irradiation damage in Ti–6Al–4V and Ti–6Al–4V–1B: Study of the microstructure and mechanical properties. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 365, pages 515-521.
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Gary S. Was. 2006. Materials Science and Technology. Materials Science and Technology 1 117 .
Mukesh Bachhav, G. Robert Odette & Emmanuelle A. Marquis. (2014) Microstructural changes in a neutron-irradiated Fe–15 at.%Cr alloy. Journal of Nuclear Materials 454:1-3, pages 381-386.
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Christian Dethloff, Ermile Gaganidze & Jarir Aktaa. (2014) Quantitative TEM analysis of precipitation and grain boundary segregation in neutron irradiated EUROFER 97. Journal of Nuclear Materials 454:1-3, pages 323-331.
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B.Z. Margolin, E.V. Yurchenko, A.M. Morozov & D.A. Chistyakov. (2014) Prediction of the effects of thermal ageing on the embrittlement of reactor pressure vessel steels. Journal of Nuclear Materials 447:1-3, pages 107-114.
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Janelle P. Wharry & Gary S. Was. (2014) The mechanism of radiation-induced segregation in ferritic–martensitic alloys. Acta Materialia 65, pages 42-55.
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Gang XU, Linling CAI, Liu FENG, Bangxin ZHOU, Wenqing LIU & Junan WANG. (2013) SEGREGATION OF ATOMS ON THE INTERFACES IN THE RPV MODEL STEEL STUDIED BY APT. ACTA METALLURGICA SINICA 48:7, pages 789-796.
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Takeshi Toyama, Yasuyoshi Nagai, Abderrahim Al Mazouzi, Masahiko Hatakeyama, Masayuki Hasegawa, Tadakatsu Ohkubo, Eric Van Walle & Robert Gerard. (2013) Intergranular Segregation in the Pressure Vessel Steel of a Commercial Nuclear Reactor Studied by Atom Probe Tomography. MATERIALS TRANSACTIONS 54:11, pages 2119-2124.
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C. English & J. Hyde. 2012. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 169 196 .
C. English & J. Hyde. 2012. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 151 180 .
S.F. Di Martino, R.G. Faulkner & R. Smith. (2011) Modelling radiation damage effects on a bcc iron lattice containing phosphorous impurity atoms near symmetrical tilt boundaries. Journal of Nuclear Materials 417:1-3, pages 1058-1062.
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Boris B. Straumal, Sergei V. Dobatkin, Alexei O. Rodin, Svetlana G. Protasova, Andrei A. Mazilkin, Dagmar Goll & Brigitte Baretzky. (2011) Structure and Properties of Nanograined Fe-C Alloys after Severe Plastic Deformation. Advanced Engineering Materials 13:6, pages 463-469.
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Boris Straumal, A.O. Rodin, A.L. Petelin, Brigitte BaretzkySvetlana Protasova, S.V. DobatkinJ. Dutta Majumdar & I. Manna. (2011) Grain Boundary Segregation and Amount of Bulk Carbides in Severely Deformed Fe–C Alloys. Defect and Diffusion Forum 309-310, pages 51-62.
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M. R. Wootton, R. Moskovic, C. J. Bolton, P. E. J. Flewitt, Jeremy T. Busby, Brady Hanson & S. W. Dean. (2010) Magnox Steel Reactor Pressure Vessel Monitoring Schemes—An Overview. Journal of ASTM International 7:1, pages 101948.
Crossref
Pavel LejcekPavel Lejček. 2010. Grain Boundary Segregation in Metals. Grain Boundary Segregation in Metals 173 201 .
Z. Lu, R.G. Faulkner & T.S. Morgan. (2008) Formation of austenite in high Cr ferritic/martensitic steels by high fluence neutron irradiation. Journal of Nuclear Materials 382:2-3, pages 223-228.
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Y. Nishiyama, K. Onizawa, M. Suzuki, J.W. Anderegg, Y. Nagai, T. Toyama, M. Hasegawa & J. Kameda. (2008) Effects of neutron-irradiation-induced intergranular phosphorus segregation and hardening on embrittlement in reactor pressure vessel steels. Acta Materialia 56:16, pages 4510-4521.
Crossref
Z. Lu, R.G. Faulkner, G. Was & B.D. Wirth. (2008) Irradiation-induced grain boundary chromium microchemistry in high alloy ferritic steels. Scripta Materialia 58:10, pages 878-881.
Crossref
Z. Lu, R.G. Faulkner & P.E.J. Flewitt. (2007) Irradiation-induced impurity segregation and ductile-to-brittle transition temperature shift in high chromium ferritic/martensitic steels. Journal of Nuclear Materials 367-370, pages 621-626.
Crossref
. 2007. Fundamentals of Radiation Materials Science. Fundamentals of Radiation Materials Science 231 266 .
Z. Lu, R.G. Faulkner & P.E.J. Flewitt. (2006) The role of irradiation-induced phosphorus segregation in the ductile-to-brittle transition temperature in ferritic steels. Materials Science and Engineering: A 437:2, pages 306-312.
Crossref
Z. Lu, R.G. Faulkner, N. Sakaguchi, H. Kinoshita, H. Takahashi & P.E.J. Flewitt. (2006) Effect of hafnium on radiation-induced inter-granular segregation in ferritic steel. Journal of Nuclear Materials 351:1-3, pages 155-161.
Crossref
Zheng Lu & Roy G Faulkner. (2011) Irradiation Assisted Grain Boundary Segregation in Steels. MRS Proceedings 981.
Crossref

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