Effect of Mesostructural Elements on Radiation-Induced Porosity in 16Cr-19Ni-2Mo-2Mn-Nb-Ti-V-P-B Austenitic Steel

Abstract:

Different mesostructural elements of 16Cr-19Ni-2Mo-2Mn-Nb-Ti-B austenitic steel have been examined after neutron irradiation to damage dose up to 82 dpa by scanning electron microscopy using orientation microscopy (EBSD). Radiation porosity with maximum void size up to 200 nm was observed in austenitic steel structure after neutron irradiation. Nonuniformity, related to mesostructural elements, such as general grain boundaries, special CSL boundaries Σ3 (twins), areas with high density of low-angle boundaries, is typical for radiation porosity.

• Periodical: Materials Science Forum (Volume 946)
• Pages: 357-361
• DOI: https://doi.org/10.4028/www.scientific.net/MSF.946.357
• Online since: February 2019
• Authors: Vladimir I. Pastukhov*, Irina A. Portnykh, Mikhail L. Lobanov
• Keywords: Austenitic Steel, CSL Boundaries, Neutron Irradiation, Orientation Microscopy, Scanning Electron Microscopy, Swelling

References

[1] B.A. Vasilyev, N.G. Kuzavkov, O.V. Mishin, A.A. Radionycheva, M.R. Farakshin,Yu.K. Bibilashvili, Yu.A. Ivanov, A.V. Medvedev, N.M. Mitrofanova, A.V. Tselishchev, L.M. Zabudko, V.I. Matveev, Yu.S. Khomyakov, V.A. Cherny, BN-600 reactor core modernization experience and prospects, Izvestia visshikh uchebnikh zavedeniy. Yadernaya energetika 1 (2001) 158−168.

[2] M.V. Bakanov, V.V. Maltsev, N.N. Oshkanov et al., The main results of structural materials operation in BN-600 reactor cores, Izvestia visshikh uchebnikh zavedeniy. Yadernaya energetika 1 (2011) 177−186.

[3] V.S. Ageev, Yu.P. Budanov, A.G. Ioltukhovsky et al., Structural materials for Russian fast reactor cores. Current status and prospects, Izvestia visshikh uchebnikh zavedeniy. Yadernaya energetika 2 (2009) 210−218.

[4] Comprehensive Nuclear Materials, Editor-in-chief: Rudy J. M. Konings, V 1, Elsevier Ltd, Amsterdam, (2012).

[5] J.O. Stiegler, The effect of thermo-mechanical treatments on void formation in irradiated stainless steel, J. Nucl. Mater. 41 (1971) 341-344.

DOI: 10.1016/0022-3115(71)90171-1

[6] H.R. Brager, The effects of cold working and pre-irradiation heat treatment on void formation in neutron-irradiated type 316 stainless steel, J. Nucl. Mater. 57 (1975) 103-118.

DOI: 10.1016/0022-3115(75)90184-1

[7] T.A. Kenfield, W.K. Appleby, H.J. Busboom, W.L. Bell, Swelling of type-316 stainless steel at high fluences in EBR-II, J. Nucl. Mater. 75 (1978) 85-97.

DOI: 10.1016/0022-3115(78)90031-4

[8] V.A. Krasnoselov, V.I. Prokhorov, A.N. Kolesnikov, Z.A. Ostrovskii, Effect of preliminary heat and mechanical treatment on 0Cr-16Ni-15Mo-ЗNb stainless steel, At Energy 54 (1983) 121-124.

DOI: 10.1007/bf01123292

[9] K. Uematsu, T. Kodama, U. Ishida, K. Suzuki, M. Koyama, Swelling Behavior of Cold Worked Type 316 Stainless Steel, in Radiation Effects in Breeder Reactor Structural Materials, M. L. Bleiberg and J. W. Bennett, Eds., the Metallurgical Society of the American Institute of Mining, Metallurgical and Petroleum Engineers, 571-589.

[10] W.K. Appleby, E.E. Bloom, J.E. Flinn, F.A. Garner, Swelling in Neutron-Irradiated 300 Series Stainless Steels, in Radiation Effects in Breeder Reactor Structural Materials, M. L. Bleiberg and J. W. Bennett, Eds., the Metallurgical Society of the American Institute of Mining, Metallurgical and Petroleum Engineers, 509-527.

[11] A.V. Kozlov, I.A. Portnykh, Conditions for the achievement of the stage of stationary radiation swelling, Phys. Met. Metallogr. 103 (2007) 105-109.

DOI: 10.1134/s0031918x07010139

[12] H.R. Brager, F.A. Garner, The Influence of Cold Work Level, Solute and Helium Content on the Swelling of Pure, AISI 316 (Fe-17Cr-16.7Ni-2.5Mo), Effects of Radiation on Materials: Eleventh Conference, ASTM STF 782, H. R. Brager and J. S. Perrin, Eds., American Society for Testing and Materials, 1982, 152-165.

DOI: 10.1520/stp34344s

[13] M. Itoh, S. Onose, S. Yuhara, Void Swelling and Microstructural Change in Neutron Irradiated Type 316 Stainless Steel, Radiation-Induced Changes in Microstructure: 13th International Symposium (Part I), ASTM STP 955, F. A. Garner, N. H. Packan, and A. S. Kumar, Eds., American Society for Testing and Materials, Philadelphia, (1987) 114-126.

DOI: 10.1520/stp33812s

[14] M. Sekine, N. Sakaguchi, M. Endo, H. Kinoshita, S. Watanabe, H. Kokawa, S. Yamashita, Y. Yano, M. Kawai, Grain boundary engineering of austenitic steel PNC316 for use in nuclear reactors, J. Nucl. Mater. 414 (2011) 232-236.

DOI: 10.1016/j.jnucmat.2011.03.049

[15] V.I. Pastukhov, S.А. Аverin, V.L. Panchenko, I.А. Portnykh, P.D. Freyer, L.A. Giannuzzi, F.А. Garner, Application of backscatter electrons for large area imaging of cavities produced by neutron irradiation, J. Nucl. Mater. 480 (2016) 289-300.

DOI: 10.1016/j.jnucmat.2016.07.059

[16] A.V. Kozlov, Dependence of the concentration of point defects in the ChS-68 austenitic steel on the rate of their generation and temperature upon neutron irradiation, Phys. Met. Metallogr. 107 (2009) 534-541.

DOI: 10.1134/s0031918x09060027