The Effect of Microstructure and Temperature Gradient on Radiation-Induced Swelling of Austenitic Steel

Author:

Pastukhov Vladimir1,Averin Sergey2,Lobanov Mikhail L.1

Affiliation:

1. Ural Federal University named after the first President of Russia B. N. Yeltsin

2. Research Institute of Nuclear Materials

Abstract

Radiation porosity through-thickness of the fuel pin cladding, made of 16Cr-19Ni-2Mo-2Mn-Nb-Ti-V-P-B steel, has been studied with scanning electron microscopy using backscattered electron (BSE) detector. The examined sample was irradiated at a temperature around 480 °С up to an integral damage dose of 87 dpa. It was shown that, due to the temperature gradient through the cladding thickness, the average size of radiation voids reduces, and their concentration increases from internal to external surface. Local nonuniformity of radiation porosity is observed in regions close to internal and external surfaces. It was shown that, non-uniformity of radiation porosity is determined by the material structure, microtwin density and high concentration of low-angle inter-granular boundaries, in particular.

Publisher

Trans Tech Publications, Ltd.

Subject

Condensed Matter Physics,General Materials Science,Atomic and Molecular Physics, and Optics

Reference19 articles.

1. G.S. Was, Fundamentals of Radiation Materials Science. Metals and Alloys, Springer-Verlag New York, (2017).

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. A.V. Kozlov, E.N. Sherbakov, O.I. Osiptsov et al., Formation and evolution of radiation clusters in FCC metals at low-temperature neutron irradiation to low dpa. Inorganic Materials: Applied Research 1 (2006) 9–17.

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