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Reference Number EP/R043973/1
Title enabling Sixty Years creep-fatigue life of the NExt generation nuclear Reactors 'SYNERgy'
Status Started
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) 100%
UKERC Cross Cutting Characterisation Not Cross-cutting 100%
Principal Investigator Professor B Chen
No email address given
Department of Engineering
University of Leicester
Award Type Standard
Funding Source EPSRC
Start Date 01 March 2019
End Date 29 February 2024
Duration 60 months
Total Grant Value £1,247,261
Industrial Sectors Energy
Region East Midlands
Programme Energy : Energy
 
Investigators Principal Investigator Professor B Chen , Department of Engineering, University of Leicester (100.000%)
  Industrial Collaborator Project Contact , EDF Energy (0.000%)
Project Contact , EURATOM/CCFE (0.000%)
Project Contact , University of Manchester (0.000%)
Project Contact , National Nuclear Laboratory (0.000%)
Project Contact , East China University of Science and Technology (ECUST) (0.000%)
Project Contact , CEA (Commissariat à l'Énergie Atomique), France (0.000%)
Project Contact , Nuclear AMRC (0.000%)
Project Contact , Henry Royce Institute (0.000%)
Project Contact , Directorate General Joint Research Centre (JRC), Belgium (0.000%)
Project Contact , State Nuclear Power Technology Corporation Limited, China (0.000%)
Web Site
Objectives
Abstract The science and engineering of materials have been fundamental to the success of nuclear power to date. They are also the key to the successful deployment and operation of a new generation of nuclear reactor systems. The next-generation nuclear reactors (Gen IV) operating at temperatures of 550C and above have been previously studied to some extent and in many cases experimental or prototype nuclear systems have been operated. For example, the UK was the world-leading nation to operate the Dounreay experimental sodium-cooled fast nuclear reactor (SFR) for ~19 years and a prototype fast reactor for ~20 years. However, even for those SFRs with in total of 400 reactor-years international operating experience, their commercial deployment is still held up. A formidable challenge for the design, licensing and construction of next-generation Gen IV SFRs or the other high-temperature nuclear reactors is the requirement to have a design life of 60 years or more.The key degradation mechanisms for the high-temperature nuclear reactors is the creep-fatigue of steel components. When structural materials are used at high temperature, thermal ageing and inelastic deformation lead to changes in their microstructures. The creep and creep-fatigue performance of structural materials are limited by the degradation of microstructures. The underlying need is to develop improved understanding and predictive models of the evolution of the key microstructural features which control long-term creep performance and creep-fatigue interaction. This Fellowship will use an integrated experimental and modelling approach covering different length and time scales to understand and predict the long-term microstructural degradation and creep-fatigue deformation and damage process. I will then use the new scientific information to make significant technological breakthroughs in predicting long-term creep-fatigue life that include microstructural degradation process. I will thereby realise a radical step beyond the current phenomenological or a functional form of constitutive models which received very limited success when extrapolated to long-term operational conditions. This research will put me and the UK at the forefront of nuclear fission research. This Fellowship will enable the 60 years creep-fatigue life of the next-generation high-temperature nuclear systems by developing a materials science underpinned and engineering based design methodology and implement it into future versions of high-temperature nuclear reactor design codes. In consequence, Gen IV reactor technologies will become commercially viable and Gen IV SFRs will be built globally to provide an excellent solution for recycling today's nuclear waste. This fellowship aims to influence the international organisations responsible for the next-generation nuclear design codes and gaining an early foothold in the international nuclear R&D via this research will give the best chance to secureThe science and engineering of materials have been fundamental to the success of nuclear power to date. They are also the key to the successful deployment and operation of a new generation of nuclear reactor systems. The next-generation nuclear reactors (Gen IV) operating at temperatures of 550C and above have been previously studied to some extent and in many cases experimental or prototype nuclear systems have been operated. For example, the UK was the world-leading nation to operate the Dounreay experimental sodium-cooled fast nuclear reactor (SFR) for ~19 years and a prototype fast reactor for ~20 years. However, even for those SFRs with in total of 400 reactor-years international operating experience, their commercial deployment is still held up. A formidable challenge for the design, licensing and construction of next-generation Gen IV SFRs or the other high-temperature nuclear reactors is the requirement to have a design life of 60 years or more.The key degradation mechanisms for the high-temperature nuclear reactors is the creep-fatigue of steel components. When structural materials are used at high temperature, thermal ageing and inelastic deformation lead to changes in their microstructures. The creep and creep-fatigue performance of structural materials are limited by the degradation of microstructures. The underlying need is to develop improved understanding and predictive models of the evolution of the key microstructural features which control long-term creep performance and creep-fatigue interaction. This Fellowship will use an integrated experimental and modelling approach covering different length and time scales to understand and predict the long-term microstructural degradation and creep-fatigue deformation and damage process. I will then use the new scientific information to make significant technological breakthroughs in predicting long-term creep-fatigue life that include microstructural degradation process. I will thereby realise a radical step beyond the current phenomenological or a functional form of constitutive models which received very limited success when extrapolated to long-term operational conditions. This research will put me and the UK at the forefront of nuclear fission research. This Fellowship will enable the 60 years creep-fatigue life of the next-generation high-temperature nuclear systems by developing a materials science underpinned and engineering based design methodology and implement it into future versions of high-temperature nuclear reactor design codes. In consequence, Gen IV reactor technologies will become commercially viable and Gen IV SFRs will be built globally to provide an excellent solution for recycling today's nuclear waste. This fellowship aims to influence the international organisations responsible for the next-generation nuclear design codes and gaining an early foothold in the international nuclear R&D via this research will give the best chance to secureIntellectual Property and return long term economic gains to our UKIntellectual Property and return long term economic gains to our UK
Publications (none)
Final Report (none)
Added to Database 10/04/19