Effect of neutron irradiation on iodine stress corrosion cracking susceptibility of zircaloy-2 tubing.

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概要

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• The effect of neutron irradiation on the iodine stress corrosion cracking (SCC) of Zircaloy-2 tubing of 8×8 type design was studied by means of ring tension test, using specimens unirradiated and irradiated to 3.2×10<SUP>19</SUP> and 3.0×10<SUP>20</SUP> n/cm<SUP>2</SUP> (E>1 MeV). The SCC threshold stresses were determined from constant load tests and the SCC initiation stresses were defined from constant cross-head rate tests. Both stresses increased with increasing neutron fluence, reaching a maximum at a neutron fluence between 1019 and 10<SUP>20</SUP> n/cm<SUP>2</SUP> and then decreased. The tendency is qualitatively in good agreement with the hypothetical conclusion derived by Lunde & Videm, for SCC failure stresses from internal gas pressurization tests on various Zircaloy cladding tubes irradiated at different reactor conditions. The cause of the increase in the SCC susceptibility at neutron fluences above 10<SUP>20</SUP> n/cm<SUP>2</SUP> would be ascribed to radiation anneal hardening phenomenon and resultant inhomogeneous incipient deformation characterized by dislocation channels.

• 一般社団法人 日本原子力学会の論文

著者

• NARUI Minoru

  The Oarai Branch, The Research Institute for Iron, Steel and Other Metals, Tohoku University

関連論文

• Effect of neutron irradiation on iodine stress corrosion cracking susceptibility of zircaloy-2 tubing.

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