By K L Murty
Gentle water reactors are the important category of nuclear energy reactors in operation this present day. even if, getting older and degradation can effect either the functionality and lifelong of parts. wisdom of those components is consequently serious to the supply of secure, non-stop operation in both the quick or lengthy term. Routes to degree and mitigate those getting older and degradation difficulties, and to evaluate residual lifetime, are severe to the fabrics administration, upkeep and security making plans for the plant.The editor and individuals supply a complete and systematic overview of fabrics getting older and degradation mechanisms well-known in mild water reactor environments, the explicit results at the major reactor elements, and the appropriate mitigation routes and fabrics administration techniques used to address those results. half one introduces basic getting older matters and degradation mechanisms and discusses corrosion in pressurized water reactors and creep deformation of fabrics in mild water reactors. next sections examine fabrics getting older and degradation in particular mild water reactor elements along the getting older of electrical cables and concentrate on fabrics administration recommendations for gentle water reactors, pressurized water reactors and VVER reactors. the belief explores materials-related difficulties confronted through mild water reactor operators and corresponding learn wishes.
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Additional info for Materials ageing and degradation in light water reactors: Mechanisms and management
Example text
Lemaire, ‘Learning from EDF investigations on SG divider plates and vessel head nozzles. Prior deformation effect on stress corrosion cracking,’ Fontevraud 7, Avignon (France), 2010. 16. F. Vaillant, S. Le Hong, C. Amzallag and C. Bosch, ‘Crack growth rates on vessel penetrations in alloy 600 in primary water,’ Fontevraud 4, 1998. 17. F. , ‘Crack growth rates in thick materials of alloy 600 and weld metals of alloy 182 in laboratory primary water. Comparison with field experience,’ Fontevraud 5, 2002.
FAC rate decreases when the flow velocity decreases and when the pH increases. FAC stops as soon as oxygen is dissolved in water. FAC affects carbon steel piping of the secondary circuit where water or wet steam circulates. Pitting is a localized corrosion forming holes at the surface of the metal, induced by the local depassivation of an area, which becomes anodic while a large area becomes cathodic. The acidity inside the pit is sustained by the spatial separation of the cathodic and anodic half-reactions, which creates a potential gradient and the transport of anions into the pit.
VVER-1000 and typical PWR, 349 VVER-4403, 348 strength, 175 stress corrosion cracking (SCC), 74, 249, 270, 329 stress induced preferential absorption (SIPA), 41, 140, 228 stress induced preferential nucleation (SIPN), 41, 140 stress intensity factor, 14 structures and components (SC), 338, 343–4 subgrain size, 107 superplasticity, 100 surface scratch technique, 97 systems, structures and components (SSC), 338, 343–4 temperature, 288–9 temperature-normalised stress term, 104 tensile test, 294 thermal creep, 132 thermal oxidation, 288 © Woodhead Publishing Limited, 2013 414 Index thermocouple (T/C) extension wires, 285 three power law creep, 102–3 time domain reflectometry (TDR), 296, 300–1 time-limited ageing analyses (TLAA), 356 validation, 370–6 containment, civil structures and structural components, 374–6 issue, 371 mechanical components, 371–3 operational limits and conditions, 374 reactor pressure vessel and internals, 373 required analyses scope, 370–1 revalidation/reconstitution, 376 role in LTO justification, 370 transient creep see primary creep transversal breaks boiling water reactor (BWR), 254–5 schematic diagram, 255 pressurised water reactor (PWR), 255 schematic diagram, 256 Voda Voda Energo Reactor (VVER), 255 schematic diagram, 256 treeing, 288 tube support plate (TSP), 327 ultrasonic testing, 274, 320 uniform corrosion, 45–6, 73–4 UO2 fuel, 387–8 upper yield point, 26 vessel head penetration (VHP), 316 viscous glide, 100–3, 102 creep behaviour of class-A type materials, 101 deformation microstructure in Nb-modified Zr-alloy crept in the three power law regime, 103 dislocation pile up and enhanced dislocation activity in grain boundary vicinity, 101 microstructural features, 103 visual examination, 274–5 visual inspection, 294 Voda Voda Energo Reactor (VVER), 157 axial cracks, 258 fuel assembly, 247 materials management strategies, 335–81 operation description, 340–3 VVER-440 basic design features, 341–2 VVER-1000 basic design features, 342–3 plant operational experience, 343–55 ageing of electrical systems and I&C, 353–5 ageing of mechanical components, 345–52 ageing of structures, 352–3 plant condition evaluation method, 343–5 plant programmes for long-term operation, 377–81 safety for long-term operation, 355–76 transversal breaks, 255 schematic diagram, 256 VVER-440, 341–2, 381 VVER-1000, 336, 340, 342–3, 354, 381 ageing of containment structures, 353 ageing of mechanical components, 350–2 VVER-440/213, 336–7, 338, 340, 341, 354, 372, 375, 380, 381 ageing management peculiarities, 364–5 containments, 352–3 reactor pressure vessel, 345–8 steam-generator design, 348–50 materials in VVER-440 vs.