Development of versatile liquid metal testing facility for lead-cooled fast reactor technology

Lead Research Organisation: University of Manchester
Department Name: Mechanical Aerospace and Civil Eng

Abstract

Liquid-metal-cooled nuclear reactors are advanced nuclear reactor designs where the primary coolant is a liquid metal, such as sodium, lead or a lead-bismuth mixture. The excellent heat transfer properties of liquid metals, and the possibility to operate liquid metal reactors at ambient pressure and very high temperature, are the main advantages of liquid metal cooled reactors with respect to water-cooled reactor designs. These advantages result in smaller and much safer reactor designs, particularly suited for small-modular construction.
Originally developed for marine propulsion, liquid-metal-cooled nuclear reactors are currently being investigated for power production. In particular, two out of the six nuclear reactor designs identified by the Generation IV International Forum and currently being researched for near-term commercial application are liquid metal reactors: the sodium-cooled fast reactor and the lead-cooled fast reactor.
The present research study, in particular, is focused on the lead-cooled fast reactor technology. Lead-cooled nuclear reactors will be deployed in small and modular units featuring long-life, pre-manufactured cores that can run for several years before being replaced, thus making these reactors also suitable for emerging and developing countries that do not plan to build their own nuclear infrastructure. The excellent heat transfer capabilities of liquid lead, together with its high boiling point, assure that decay heat after reactor shutdown can be safely dissipated with entirely passive means, thus resulting in a particularly safe nuclear reactor design. Lead is also very dense and therefore a good shield against gamma radiations, which is a bonus for protecting the operators and the environment. Unlike sodium that burns in contact with air and that can explode in contact with water, lead does not react significantly with either air or water, allowing simpler and cheaper system design and a safer plant operation.
Currently, the main drawback of the lead-cooled nuclear reactor technology is the very limited knowledge of erosion and corrosion of materials exposed to liquid lead at temperatures representative of nuclear reactor operation. This is the knowledge gap that the present research aims to address: erosion and corrosion tests will be carried out in liquid lead at nuclear reactor operating conditions to identify the most promising materials to realize the reactor structural components. High-fidelity CFD simulations of the experimental setup, will first assist with the design of the experimental facility and then provide the missing information on the local flow and thermal fields, necessary to fully understand the implications of the experimental data and apply the experimental findings more widely to corrosion/erosion analysis of lead-cooled reactors.
Additionally, the present research will also develop an imaging technology based on ultrasounds to inspect the reactor internals during operation. Liquid metals, in fact, are opaque and conventional imaging techniques therefore not applicable. The possibility to periodically inspect the reactor internals is essential for safe and profitable operation.

Planned Impact

Two of the main cornerstones of the UK energy policy are energy security and environmental sustainability. The UK is committed to reducing carbon emissions to 80% of their 1990 levels by 2050. The UK is decarbonising its economy with a reduction of 42% in carbon emissions while at the same time increasing its GDP by 67% (period 1990-2016). This is accomplished by replacing electricity production from fossil fuels with production from low carbon emission and renewable sources. A key point, highlighted in the Government's "Clean and Growth Strategy", is to diversify to different types of clean technologies to strengthen the power generation sector. Nuclear energy plays an important role in this energy mix to further decrease the carbon footprint of electricity production, as evidenced by the UK Government's investment in a 3.2GW nuclear power plant at Hinkley Point C, expected to supply 7% of the UK electricity demand.
The long-term disposal of spent nuclear fuel from past and current generation reactors remains a long term issue, as a solution based on deep geological disposal facilities finds little support from local communities. The UK also currently stores civilian stockpiles of separated plutonium. The proposed research supports the development of Generation IV, innovative fast reactor designs, which can use spent fuel from current reactors and also separated plutonium, thereby providing a more sustainable solution to the problem of spent fuel, as well as carbon-free power generation. These reactor designs are also relevant to naval propulsion, an area where UK needs to retain its expertise and industry. The proposed research, in the short term supports the development of lead cooled reactors by advancing current understanding of lead's corrosive characteristics, and in the longer term through facilitating the development of reliable turbulence models for the efficient and fast simulation of lead cooling processes.
Moreover, the proposed research, through its generation of high-fidelity data for low-Prandtl number thermal processes, will a) extend knowledge on the characteristics of the poorly-understood low-Prandtl-number heat convection and b) enable the development of more reliable simulation methods for heat convection in high-conductivity liquids. The proposed research thus has a fundamental scientific impact as well as impact in the more applied topic of a lead-cooled reactor design.
 
Description By optimising the shape of the samples used in the rotating cage it is possible to extend the methodology to liquid lead, overcoming its high density.
The flow developmen over the samples revealed by the Computational Fluid Dynamics simulations will facilitate the interpretation of the corrosion measurements.
Exploitation Route Optimized samples shape now extended to corrosion in more conventional liquids
Sectors Energy

 
Description Development of versatile liquid metal testing facility for lead-cooled fast reactor technology 
Organisation University of Pittsburgh
Department Swanson School of Engineering
Country United States 
Sector Academic/University 
PI Contribution The University of Pittsburgh undertook to develop an experimental facility to study accelerated liquied lead corrosion and the University of Manchester undertook to carry out Computational Fluid Dynamics simulations of the experiments; preliminary simulations to enable the University of Pittsburgh to develop a more effective design of the experimental rig and once the experimental data became available high fidelity simulations to help interpret the data. The preliminary simulations with a number of design reccomendations, for the facility in general and for the shape of the corrosion samples in particular, were supplied to the Pittsburgh team, but due to delays in the development of the experimental facility, as a result of the COVID pandemic, the experimental data were not available before the end of the funding period.
Collaborator Contribution The Pittsburgh team provided the Manchester team details of the original design of the accelerated lead corrosion rig and of the corresponding operating conditions which are used in the initial Computational Fluid Dynamics simulations.
Impact The main outputs of this collaboration are: 1. The development of a Computational Fluid Dynamics model of the accelerated lead corrosion experimental facility by the CFD experts at Manchester, based on information supplied by the corrosion experts at Pittsburgh. 2. Use of the CFD model in Manchester to make reccommendation on how to make design imporovements to the experimental facility and on how to relate the corrosion findings to the flow development over the corrosion samples.
Start Year 2020
 
Description CCP/SIG NTH Annual Technical Meeting 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Professional Practitioners
Results and Impact CCP/SIG NTH Annual Technical Meeting-The Collaborative Computational Project in Nuclear Thermal Hydraulics Working Group
Year(s) Of Engagement Activity 2021
URL https://ccpnth.ac.uk/?tribe_events=the-2021-annual-technical-meeting-of-ccp-nth
 
Description Dalton seminar series: Research showcase - PDRA focus 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach Local
Primary Audience Postgraduate students
Results and Impact Seminar hosted by Dalton Nuclear Institute to showcase nuclear-related research
Year(s) Of Engagement Activity 2021
 
Description MACE Aerospace and Thermofluids Research Seminars 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Postgraduate students
Results and Impact Seminar hosted by the Department of Mechanical, Aerospace and Civil Engineering of the University of Manchester, attended by academics, postdocs, PhD students and some undergraduate students
Year(s) Of Engagement Activity 2021
 
Description The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Professional Practitioners
Results and Impact There was a 20-minute presentation of the CFD modelling of the accelerated lead corrosion experimental rig, with discussion of the flow physics involved and the resulting design implications. This was followed by questions from the audience.
Year(s) Of Engagement Activity 2022