Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
7965449 | Journal of Nuclear Materials | 2015 | 17 Pages |
Abstract
A complex study of structural state and properties of 18Cr-10Ni-Ti austenitic stainless steel after irradiation in BOR-60 fast research reactor (in the temperature range 330-400 °С up to damaging doses of 145 dpa) and in VVER-1000 light water reactor (at temperature â¼320 °С and damaging doses â¼12-14 dpa) was performed. The possibility of recovery of structural-phase state and mechanical properties to the level almost corresponding to the initial state by the recovery annealing was studied. The principal possibility of the recovery annealing of pressurized water reactor internals that ensures almost complete recovery of its mechanical properties and microstructure was shown. The optimal mode of recovery annealing was established: 1000 °C during 120 h.
Keywords
DPAIASCCPWRBWREDXSNPPRISEELSSAEDIrradiationTemRecovery annealingPhase compositionStructural changesDisplacement per atomRadiation-induced segregationBoiling water reactorPressurized Water ReactorStemelectron energy loss spectrometryX-ray energy dispersive spectroscopyStainless steelSEMscanning transmission electron microscopyScanning electron microscopyTransmission electron microscopynuclear power plantSelected Area Electron Diffraction
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
B.A. Gurovich, E.A. Kuleshova, A.S. Frolov, D.A. Maltsev, K.E. Prikhodko, S.V. Fedotova, B.Z. Margolin, A.A. Sorokin,