Creep and Creep-Fatigue Crack Growth Mechanisms in Alloy 709

Lead Research Organisation: University of Birmingham
Department Name: Metallurgy and Materials

Abstract

Predicting crack growth lives of components that are subject to long times under stress in complex operating cycles and environments is one essential element in underpinning any proposed flaw evaluation procedure for both next generation advanced nuclear reactors and for the extension of life of existing reactors (such as the UK fleet of Advanced Gas Cooled Reactors, AGRs). The proposed research will contribute to the scientific understanding of mechanisms of creep-crack growth, creep-fatigue crack growth and dwell-fatigue crack growth in a specific stainless steel alloy. Flaw evaluation procedures in future nuclear reactors can then be based with more confidence on models of materials' behaviour underpinned by increased physical understanding. In particular the study will address how results obtained from accelerated tests can be applied appropriately to predict flaw extension behaviour under envisaged operating conditions (over a design lifetime of sixty years).

Planned Impact

This programme seeks to develop UK capability in next generation nuclear reactor technologies in close collaboration with US collaborators. Beneficiaries will include:
(i) UK industry- where the mechanistic understanding of a new generation austenitic stainless steel alloy will impact on its future use in the next generation of nuclear fission reactors. The alloy has the potential to allow improved reactor economics, increased safety margins and design flexibility. A comparison of this new alloy with existing alloys in use may contribute to the assessment of life extension methodologies for the current UK fleet of nuclear reactors;
(ii) UK society and public- the provision of safe, efficient and reliable nuclear power both now and in the future is seen as vital to UK energy policy. Improvements in design, reliable operation, increased safety margins and life extension all deliver benefits which can be appreciated readily by the general public;
(iii) UK policy makers- such joint international programmes and studies have the potential to inform and to influence important future energy policy decisions for the UK. International endorsement and appreciation of the quality of UK research contributions is critical in allowing RCUK to argue the case for continued ( and increased) investment in the UK science base for basic research which has strong technological and economic benefits.

Publications

10 25 50
 
Description Comprehensive analysis of high temperature deformation and crack growth of this new alloy and demonstration that it has improved capabilities at the envisaged operating temperature when compared to previous alloys.Modified crack growth parameter unifies observations and suggest how actual components can be designed to achieve desired design life at service temperatures and stresses.
Exploitation Route US/UK nuclear industry co-operations.
Sectors Energy

 
Description This research provides one further step along the lines of the development of a sodium- cooled commercial nuclear reactor and removes one impediment to its long-term assessment in service.
First Year Of Impact 2019
Sector Energy
Impact Types Societal,Economic

 
Description University Research and Technology Centre (UTRC) with Baowu Steel
Amount £1,100,000 (GBP)
Organisation Baowu Steel 
Sector Private
Country China
Start 01/2017 
End 12/2019