Reactor Materials - Modern Status
Abstract
This paper presents short description of modern status of reactor materials for nuclear. The fast growing energy demand and concerns about climate changes require nuclear energy to play a role among other energy sources to satisfy future energy needs of mankind. Exactly core materials behaviour provides safe and economy exploitation of nuclear power plants. Metals and alloys used in nuclear service serve in very challenging environments involving high temperatures and stresses, as well as exposure to high irradiation doses. Problems of radiation resistance of materials for exploitation reactors and reactors of next generation are described.
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Rosumkov O. Ukrainian center of economic and political studies //National security and defense.-2006.-№6.-P.3.
Garner F.A. Irradiation Performance of Cladding and Structural Steels in the Liquid Metal Reactors, in Material Science and Technology // Nuclear Materials.-1994.-10A.-P.12-14.
Voyevodin V.N., Neklyudov I.M. Evolution of the structure phase state and radiation resistance of structural materials.-Kiev:Naukova Dumka,2006.-354 s.
Brumovsky M. Irradiation hardening and materials emrittlement in light water reactor (LWR) environments // Nuclear Research Institute.-2010.-Vyp.3.-P.357-373.
Eyre B.L., Maher D.M., Perrin R.C. Embrittlement in steels // Metal Phys.-1999.-№77.-P.371.
Kuleshova E.A., Gurovich B.A., Shtrombakh Ya.I. Comparision of microstructural features of radiation embrittlement of VVER-440 and VVER-1000 reactor pressure vessel steels // JNM.-2002.-Vyp 300.-P.127-140.
Морозов А.М., Филимонов Г.Н., Цуканов В.В. Основные принципы легирования сталей для корпусов атомных реакторов типа ВВЭР // Вопросы материаловедения.-2006.-№1(45).-P.103-111.
Solonin M.I., Reshetnikov F.G., Nikulina A.V. New Construction Materials for Active Zone in Nuclear Power Plants // Nuclear Materials.-2004.-Vol.25.-P.12-14.
Borodin O.V., Bryk V.V., Vasilenko R.L., Voyevodin V.N. Petelguzov I.A. Rybalchenko N.D. Influence of oxygen content on evolution of the structure of alloy Zr1%Nb under ion irradiation // Problem of atomic science and technology.-2008.-№2.-P. 53 61.
Neustroyev V.S., Golovanov V.N., Shamardin D.K., Ostrovskiy Z.Ye., Pecherin A.M. Radiation effects in Х18Н10Т steel irradiated in different reactors under conditions close to operation conditions of WWER PVI // Proceedings of VI Russian conference on reactor materials science.-2000.-Vol.3.-Part 1.-P.3-23.
Miller M.K. Understanding and mitigating ageing in nuclear power plants // Materials and operational aspects of plant life management (PLiM).-2010.-Vol.3.-P.914.
Neustroev V.S., Dvoretsky V.G., Ostrovsky Z.E., Shamardin V.K., Shimansky G.A. Studies into the Microstructure and Mechanical Properties of 18Cr10NiTi Steel after Irradiation in the WWER-1000 Core // Problems of Atomic Science and Technology.-2003.-№3(83).-P.73-78.
Garner F.A. Void swelling of austenitic internal components of PWRs and VVERs, and its possible impact on plant life extension // 5th International Conference on Nuclear and Radiation Physics.-2005.- issued in CD format.
Garner F.A., Porollo S.I., Konobeev Yu.V., Maksimkin O.P. Void swelling of austenitic steels irradiated with neutrons at low temperatures and very low dpa rates // 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems.-2005.-P.439–448.
Garner F.A. Void swelling and irradiation creep in light water reactor environments // Chapter 10 of Understanding and mitigating ageing in nuclear power plants.-2010.-Vol.6.-P.175-179.
Garner F.A., Makenas B.J. Recent experimental results on neutron-induced void swelling of AISI 304 stainless steel concerning its interactive dependence on temperature and displacement rate // Fontevraud-6 Symposium on Contribution of Materials Investigations to Improve the Safety and Performance of LWRs.-18–22 September 2006,Fontevraud, France.-P.625-636.
Kalchenko A.S., Bryk V.V., Lazarev N.P., Neklyudov I.M., Voyevodin V.N. Prediction of swelling of 18Cr10NiTi austenitic steel over a wide range of displacement rates // JNM.-2010.-Vol.399.-Issue 1.-P.114–121.
Garner F.A., Simonen E.P., Oliver B.M. Retention of hydrogen fcc metals irradiated at temperatures leading to high densities of bubbles or void // JNM.-2006.–Vol.356.–P.122–135.
Edwards D. J. Nano-cavities observed in a 316SS PWR flux thimble tube irradiated to 33 and 70 dpa //JNM.–2009.–Vol.384.–P.249–255.
Neklyudov I.M., Borodin O.V., Bryk V.V., Voyevodin V.N. Problem of Radiation Resistance of Structural Materials of Nuclear Power // Progress in High Energy Physics and Nuclear Safety.-2007.-Vol.126.-P.259-277.
Golovinski S.A., Boitsov A.V. Intl. Conf “Progress in atomic energy based on fast neutron with a closed fuel cycle. Strategy and perspectives of the international collaboration”.-Moskow, Nov.2005.-available on CD.
Garner F.A. Irradiation Performance of Cladding and Structural Steels in the Liquid Metal Reactors, in Material Science and Technology // Nuclear Materials.-1994.-Vol.10A.-P.12-14.
Voyevodin V.N., Neklyudov I.M. Evolution of the structure-phase state and radiation stability of the construction materials.-Kiev: Naukova Dumka, 2006.-387 p.
Klueh R.L., Harries D.R. High-Chromium Ferritic and Martensitic Steels for Nuclear Applications // JNM.-2001.-Vol.56.-P.71-74.
Carlan Y., Averty X., Brachet J-C., Bertin J-L. Post-Irradiation Tensile Behavior and Residual Activity of Several Ferritic/Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325 C up to 9 dpa // Journal of ASTM Intern.-2005.-P.67.
Borodin O.V., Bryk V.V., Voyevodin V.N., Kalchenko A.S., Kupriyanova Yu.E., Melnichenko V.V., Neklyudov I.M., Permyakov A.V. Radiation swelling of ferritic-martensitic steels EP-450 and HT-9 under irradiation by metallic ions to super-higher doses // Problem of atomic science and technology.-2008.-Vol.45.-P.256-258.
Borodin O.V., Bryk V.V., Neklyudov I.M., Shamardin V.K., Voyevodin V.N. Investigation of microstructure of ferritic-martensitic steels containing 9 and 13 % Cr irradiated with fast neutrons // Journal of Nuclear Materials.-1994.-Vol.207.-P.295-302.
Lanskaya K.A. High-chromic heat-proof steels.-M: Metallurgia, 1976.-216 p.
Klueh R.L., Gelles D.S., Jitsukawa S., Kimura A., Odette G.R., Schaaf B., Van der. Victoria M. Development of innovative metallic materials for applications in the nuclear industry // JNM.-2002.-Vol.455.-P.307–311.
Jitsukawa S., Kimura A., Kohyama A., Klueh R.L., Tavassoli A.A., Schaaf B., van der. Odette G.R., Rensman J.W. Materials for fission and fusion reactors // JNM.-2004.-Vol.39.-P.329–333.
Klueh R.L., Shingledecker J.P., Swindeman R.W., Hoelzer D.T. Oxide dispersion strengthened (ODS) alloy materials // JNM.-2005.-Vol.341.-P.103.
de Castro V., Leguey T., Monge M.A., Munoz A., Pareja R., Amador D.R., Torralba J.M., Victoria M. Powder metallurgy for steel production // JNM.-2003.- Vol.228.-P.322.
Ukai S., Harada M., Okada H., Inoue M., Nomura S., Shikakura S., Nishida T., Fujiwara M., Asabe K. Structural materials due to their creep rupture strength at high temperature // JNM.-1993.-Vol.74.-P.204.
Lindau R., Moslang A., Schirra M., Schlossmacher P., Klimenkov M. Nano-dispersion particles in ODS // JNM-2002.- Vol.769.-P.307–311.
Klimenkov M., Lindau R., Moslang A. TEM characterization of structure and composition of nanosized ODS particles in reduced activation ferritic-martensitic steels // JNM.-2004.-Vol.347.-P.329-333.
Miller M.K., Hoelzer D.T., Kenik E.A., Russel K.F. Nanometer scale precipitation in ferritic MA/ODS alloy MA957 // JNM.-2004. - Vol.329.-P.338-341.
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