Projects: Projects for Investigator |
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Reference Number | EP/M018040/1 | |
Title | Extension to Transferability of Small-Specimen Data to Large-Scale Component Fracture Assessment (TRANSFER-EXT) | |
Status | Completed | |
Energy Categories | Nuclear Fission and Fusion(Nuclear Fission, Nuclear supporting technologies) 100%; | |
Research Types | Basic and strategic applied research 100% | |
Science and Technology Fields | PHYSICAL SCIENCES AND MATHEMATICS (Metallurgy and Materials) 50%; ENGINEERING AND TECHNOLOGY (Mechanical, Aeronautical and Manufacturing Engineering) 50%; |
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UKERC Cross Cutting Characterisation | Not Cross-cutting 100% | |
Principal Investigator |
Professor B Ainsworth No email address given Mechanical, Aerospace and Civil Engineering University of Manchester |
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Award Type | Standard | |
Funding Source | EPSRC | |
Start Date | 01 July 2016 | |
End Date | 30 September 2016 | |
Duration | 3 months | |
Total Grant Value | £15,964 | |
Industrial Sectors | Energy | |
Region | North West | |
Programme | Energy : Energy | |
Investigators | Principal Investigator | Professor B Ainsworth , Mechanical, Aerospace and Civil Engineering, University of Manchester (100.000%) |
Web Site | ||
Objectives | ||
Abstract | The integrity of piping components of a nuclear reactor is vital to ensure the supply of coolant to the core at all times during the plant lifetime. One of the inputs to demonstrating integrity is a fracture mechanics assessment to demonstrate defect tolerance. Within the existing TRANSFER project, simplified defect assessments have been performed to estimate the loads for ductile crack initiation for both straight pipes and elbows of various pipe diameters and with various sizes of defect. The estimates have been found to be close to or conservatively predict experimentally measured loads to crack initiation, when using modern stress intensity factor and limit load solutions with the Failure Assessment Diagram (FAD) approach of the defect assessment procedure R6. Within the extension to TRANSFER, it is planned to extend this validation of practical defect assessment methods on real large-scale piping components to address the effects of constraint on the ductile tearing which occurs after crack initiation. The extension will also maximise the impact of the overall TRANSFER project through presentations at the 23rd conference on Structural Mechanics in Reactor Technology (SMiRT) to be held in Manchester in August 2015 | |
Publications | (none) |
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Final Report | (none) |
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Added to Database | 23/08/16 |