New PDF release: Corrosion Issues in Light Water Reactors: Stress Corrosion

By D Fron

ISBN-10: 184569242X

ISBN-13: 9781845692421

ISBN-10: 1845693469

ISBN-13: 9781845693466

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Additional info for Corrosion Issues in Light Water Reactors: Stress Corrosion Cracking (EFC51)

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To these can be added the experience of extensive IGSCC in the g ¢ strengthened analogue of Alloy 600, Alloy X750, which is used for split pins attaching the CRDM guide tubes to the upper core plate. Even Alloy 718, a high strength nickel base alloy containing 17–21% Cr, which is normally considered a very reliable high strength material in PWR primary water use, has occasionally exhibited IGSCC [4]. A common feature of service failures of Alloy 600 and its compatible weld metals is the presence of very high residual stresses exceeding the nominal yield strength, usually coupled with a roughly machined or heavily ground surface finish.

Silvestre, A. Trenty, ‘An analysis of baffle/former bolt cracking in French PWRs’, ASTM STP 1401 Environmentally Assisted Cracking: Predictive methods for Risk Assessment and Evaluation of Materials, Equipment and Structures, Ed. R. D. Kane, ASTM (2000) 210–223. S. M. Bruemmer, E. P. Simonen, P. M. Scott, P. L. Andresen, G. S. Was, J. L. Nelson, ‘Radiation-induced material changes and susceptibility to Intergranular failure of light-water-reactor core internals’, Journal of Nuclear Materials, 274 (1999) 299– 314.

Steels with lower yield strengths have also failed due to poor heat treatment or material variability. Hydrogen cracking is usually avoided by specifying an upper bound strength limit (normally defined by a hardness level acceptance criterion of <350HV). A second category of bolt failures has concerned the integrity of the primary pressure boundary at locations such as flanges of manway covers and valves. Most of these incidents have been caused by erosion-corrosion in PWR primary water leaks. A small number of failures among this category of bolt have been associated, however, with environment assisted cracking rather than wastage [32].

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Corrosion Issues in Light Water Reactors: Stress Corrosion Cracking (EFC51) by D Fron


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