AGR Technologies for Enabling Molten Salt-cooled Reactor Designs

Lead Research Organisation: University of Cambridge
Department Name: Engineering

Abstract

High temperature reactors most commonly use He gas as a coolant. The main disadvantage of gases however is their low, compared to liquid coolants, volumetric heat capacity, which ultimately leads to low reactor power density and hence inferior economics. Molten salts are leading candidates to replace the helium coolant in high temperature reactors due to superior heat transfer properties that would allow substantial increase in the core power density. In addition, operation at high temperature (around 700 C) would lead to high power conversion efficiency and allow the use of the reactor heat for various industrial processes. Moreover, high boiling point of molten salts (>1,200 C) would allow designs that operate at low pressure, which should reduce the cost of the reactor vessel, further contributing to economic attractiveness of the concept. Another common feature of molten salt-cooled high temperature reactor designs is the use of highly robust coated-particle TRISO fuel and a graphite moderator. In combination with chemical inertness and high heat capacity of the salt coolant, these features make excellent safety case.
One of the recently proposed variants of such system is Fluoride salt-cooled High temperature Reactor (FHR). Many options exist for the implementation of the concept which rely on combining different fuel forms, coolant salts and configurations of key components. Only a small fraction of this vast design space has been explored so far. FHRs with certain fuel designs can potentially adopt many features from the Advanced Gas cooled Reactors (AGRs) designed and being successfully operated in the UK for many years. Taking advantage of the existing AGR technology and operating experience would substantially reduce the development costs of FHRs and improve their economic attractiveness.
This project will develop a high thermal power commercial-scale FHR leveraging and adapting existing technology from the AGR, such as refuelling strategy, layout of components and maintenance approaches, as well as adapting the use TRISO particles fuel from the High Temperature Gas-cooled Reactors.
The project will identify the most attractive combination of fuel, salt coolant and core configuration with respect to economic performance and safety.
The project will be led by the University of Massachusetts at Lowell in collaboration with Massachusetts Institute of Technology, University of Cambridge, UK and AREVA as an industrial partner. The US Universities will perform the design space exploration for core and fuel cycle strategies for the base line design, while the University of Cambridge will focus on alternative options with AGR-type fuel configurations. The industrial partner will lead the economic analysis effort and contribute to the development of refuelling and maintenance strategies as well as the safety analysis tasks.

Planned Impact

Fluoride salt-cooled High temperature Reactor concept can potentially become more cost effective alternative to the existing Light Water Reactors for a number of reasons.
- Heat transport properties of molten salts are supperior to those of gases, therefore allowing to achieve similar to LWRs power density.
- Near atmospheric pressure operation, large thermal inertia and chemical intertness of molten salts lead to simpler safety systems with enhanced performance and less costly reactor components.
- High temperature operation allows high power conversion efficiency and possibility of using the heat in energy intensive industrial processes. Both of these features will increase the nuclear energy contribution to global reduction of CO2 emissions.
This project will develop a high power comercial scale FHR design variant which will make use of the UK Advanced Gas Cooled Reactor design features. Leveraging AGR technology and experience will dramatically reduce the development costs, improve the chances and speed up the path to commercialisation of FHRs paving the way to global deplyment.
Success of this and the follow up projects could lead to worldwide dissemination of the UK indiginous AGR technology and expertese, dramaticaly increasing its value, since, currently, the knowledge of AGRs is of little practical use outside the UK. Commercialisation of this type of FHR will create multiple research opportunities for the UK academic community and commercial opportunities for the UK nuclear industry.
 
Description It has been shown that salt-cooled reactors with core configuration similar to that of the existing Advanced Gas-cooled Reactors (AGR) constructed and successfully operated in the UK, can achieve substantially higher core power density.
It has been shown that within reasonably large domain of the core parameters space, the high-power density core configurations will have negative reactivity feedback in response to thermal expansion of the salt coolant. Negative reactivity feedback is essential for assuring the core stability during power demand fluctuations and for assuring passive shutdown in case of reactivity insertion accidents.
Coolant salts alternative to the reference LiF-BeF salt which do not generate tritium during operation are less attractive in terms of their capability to increase the core power density and have smaller design parameters space in which negative coolant temperature coefficient can be assured.
One of the major findings from the review of past and contemporary studies of AGRs and other high-temperature gas-cooled reactors is that graphite core structures ultimately limit the life of the reactor, as these are typically non-retrofittable. This is a serious limitation of this reactor type which nearly universally relies on graphite as the main neutron moderator.
Consideration of wider range of coolant salt options and core geometry configurationsin this project suggest that operation of ARG-like salt-cooled reactors is possible without reliance on graphite core structure. This is a major finding with far reaching implications, potentially leading to development of salt-cooled designs which are no longer limited by the life of their graphite core structure. A follow up project proposal is being developed to confirm and explore this possibility.
Exploitation Route Molten salt-cooled reactors attract a lot of interest due to their many favourable features such as high temperature but low-pressure operation. The idea has been taken forward by a commercial company in the US (Kairos Power) which will benefit from the outcomes of this project, informing their design choices and potentially speeding up the development timeline. In addition, US DOE grant has been awarded to a consortium of US universities aiming at exploring alternative salt-cooled reactor designs with many synergies and mutual benefits from information exchange with this project. The UK project team has established collaboration with OECD Nuclear Energy Agency which coordinates international project on developing and verifying modelling methods for salt-cooled reactors. UK Department of Business Energy and Industrial Strategy has established a cross-disciplinary advisory group on molten salt technologies which will benefit from the results of this project through understanding the advantages and limitations of this type of reactors.
Sectors Chemicals,Education,Energy

 
Description Contribution to BEIS Advisory Group on molten salt technologies
Geographic Reach National 
Policy Influence Type Participation in a guidance/advisory committee
 
Description Salt-cooled High-temperature Reactors
Amount £120,000 (GBP)
Funding ID 2621769 
Organisation Engineering and Physical Sciences Research Council (EPSRC) 
Sector Public
Country United Kingdom
Start 09/2021 
End 09/2025
 
Description National Nuclear Laboratory, Advanced Nuclear Fuel Cycle Programme 
Organisation National Nuclear Laboratory
Country United Kingdom 
Sector Public 
PI Contribution This research made possible a collaboration with NNL. It led to participation in a project on molten salt technologies applied to nuclear fuel cycle technology. The project was funded as part of multi-university consortium led by the University of Edinburgh on application of pyro-processing in nuclear fuel cycles. The role of Cambridge team is to investigate the implications of pyro-processing by perfroming dynamic system analysis of possible future UK fuel cycles.
Collaborator Contribution A wide range of other adjacent technologies will be studied by other universities within the consortium including fundamental molten salt chemistry, instrumentation and process engineering. The project coordinated by the National Nuclear Laboratory.
Impact The project is still ongoing. It includes regular (quarterly) mini-conferences which allow participating researches from diverse fields to learn the latest development in each area.
Start Year 2020
 
Description National Nuclear Laboratory, Advanced Nuclear Fuel Cycle Programme 
Organisation National Nuclear Laboratory
Country United Kingdom 
Sector Public 
PI Contribution This research made possible a collaboration with NNL. It led to participation in a project on molten salt technologies applied to nuclear fuel cycle technology. The project was funded as part of multi-university consortium led by the University of Edinburgh on application of pyro-processing in nuclear fuel cycles. The role of Cambridge team is to investigate the implications of pyro-processing by perfroming dynamic system analysis of possible future UK fuel cycles.
Collaborator Contribution A wide range of other adjacent technologies will be studied by other universities within the consortium including fundamental molten salt chemistry, instrumentation and process engineering. The project coordinated by the National Nuclear Laboratory.
Impact The project is still ongoing. It includes regular (quarterly) mini-conferences which allow participating researches from diverse fields to learn the latest development in each area.
Start Year 2020
 
Description US DOE NEUP project: Design of a Commercial-Scale, Fluoride-Salt-Cooled, High-Temperature Reactor with Novel Refueling and Decay Heat Removal Capabilities 
Organisation Areva
Country France 
Sector Private 
PI Contribution Information exchange between project partners
Collaborator Contribution Information exchange between project partners
Impact Information exchange between project partners. Published two joint papers.
Start Year 2018
 
Description US DOE NEUP project: Design of a Commercial-Scale, Fluoride-Salt-Cooled, High-Temperature Reactor with Novel Refueling and Decay Heat Removal Capabilities 
Organisation Massachusetts Institute of Technology
Country United States 
Sector Academic/University 
PI Contribution Information exchange between project partners
Collaborator Contribution Information exchange between project partners
Impact Information exchange between project partners. Published two joint papers.
Start Year 2018
 
Description US DOE NEUP project: Design of a Commercial-Scale, Fluoride-Salt-Cooled, High-Temperature Reactor with Novel Refueling and Decay Heat Removal Capabilities 
Organisation University of Massachusetts Lowell
Country United States 
Sector Academic/University 
PI Contribution Information exchange between project partners
Collaborator Contribution Information exchange between project partners
Impact Information exchange between project partners. Published two joint papers.
Start Year 2018