Small modular reactors (SMRs) are a type of nuclear fission reactor which are smaller than conventional reactors. This allows them to be manufactured at a plant and brought to a site to be assembled. Modular reactors allow for less on-site construction, increased containment efficiency, and enhanced safety due to passive nuclear safety features. SMRs have been proposed as a way to bypass financial and safety barriers that have inhibited the construction of large conventional nuclear reactors in recent decades.
Several designs exist for SMR, ranging from scaled down versions of existing nuclear reactor designs, to entirely new generation IV designs. Both thermal-neutron reactors and fast-neutron reactors have been proposed, as well as molten salt and gas cooled reactor models.
A main hindrance to the commercial application of SMRs as of 2015 is licensing, since current regulatory regimes are adapted to conventional nuclear power plants and have not been adapted to SMRs in terms of staffing, security etc. Time, cost and risk of the licensing process are critical elements for the construction of SMRs.
Advantages and potential uses
The main advantage of small modular reactors is that they could be manufactured and assembled at a central factory location. They can then be sent to their new location where smaller SMRs can be installed with little difficulty. However, SMR module transportation is critical and needs further studies.
Another advantage of the small reactor is that a user can install their first unit, instantly generating revenue and cash flows, then later add as many other smaller reactors as necessary — cutting back on financing times and saving on long, drawn out construction processes.
Some larger SMRs require more significant on-site construction, such as the 440 MWe 3-loop Rolls-Royce SMR, which targets a 500-day construction time.
SMRs are particularly useful in remote locations where there is usually a deficiency of trained workers and a higher cost of shipping. Containment is more efficient, and proliferation concerns could be lowered. SMRs are also more flexible in that they do not necessarily need to be hooked into a large power grid, and can generally be attached to other modules to provide increased power supplies if necessary.
The electricity needs in remote locations are usually small and highly variable. Large nuclear power plants are generally rather inflexible in their power generation capabilities. SMRs have a load-following design so that when electricity demands are low they will produce a lower amount of electricity.
Many SMRs are designed to use new fuel ideas that allow for higher burnup and longer fuel cycles. Longer refueling intervals can decrease proliferation risks and lower chances of radiation escaping containment. For reactors in remote areas, accessibility can be troublesome, so longer fuel life can be very helpful.
SMRs could be used to power significant users of energy, such as large vessels or production facilities (e.g. water treatment/purification, or mines). Remote locations often have difficulty finding economically efficient, reliable energy sources. Small nuclear reactors have been considered as solutions to many energy problems in these hard-to-reach places. Cogeneration options are also possible.
Because of the lack of trained personnel available in remote areas, SMRs have to be inherently safe. Many larger plants have active safety features that require "intelligent input", or human controls. Many of these SMRs are being made using passive or inherent safety features. Passive safety features are engineered, but do not require outside input to work. A pressure release valve may have a spring that can be pushed back when the pressure gets too high. Inherent safety features require no engineered moving parts to work. They only depend on physical laws.
Rolls-Royce aims to sell nuclear reactors for the production of synfuel for aircraft.
Operation
There are a variety of different types of SMR. Some are simplified
versions of current reactors, others involve entirely new technologies.
All current small modular reactors use nuclear fission.
When an unstable nucleus (such as 235
U) absorbs an extra neutron, the atom
will split, releasing large quantities of energy in the form of heat
and radiation.
The split atom will also release neutrons, which can then be absorbed by
other unstable nuclei, causing a chain reaction. A sustained fission
chain is necessary to generate nuclear power.
SMR designs include thermal-neutron reactors and fast-neutron reactors.
Thermal-neutron reactors rely on a moderator to slow neutrons and generally use 235
U
as fissile material. Most currently operating nuclear reactors are of
this type.
Fast reactors don't use moderators to slow down the neutrons, therefore
they rely on the nuclear fuel being able to absorb neutrons travelling
at higher speeds.
This usually means changing the fuel arrangement within the core, or
using different fuel types. 239
Pu is more likely to absorb a high-speed neutron than 235
U.
A benefit of fast reactors is that they can be designed to be breeder reactors.
As these reactors produce energy, they also let off enough neutrons to
transmute non-fissionable elements into fissionable ones.
A very common use for a breeder reactor is to surround the core in a
"blanket" of 238
U, which is the most easily found isotope of uranium.
Once the 238
U undergoes a neutron absorption reaction, it becomes 239
Pu, which can be removed from the reactor once it is time to refuel, and used as more fuel once it has been cleaned.
Cooling
Currently, most reactors use water as a coolant. New reactor designs are experimenting with different coolant types. Liquid metal cooled reactors have been used both in the United States and other countries for some time. Gas cooled reactors and molten salt reactors are also being looked at as an option for very high temperature operation.
Thermal/electrical generation
Traditionally, nuclear reactors use a coolant loop to heat water into steam, and use that steam to run turbines to generate electricity. Some new gas-cooled reactor designs are meant to drive a gas-powered turbine, rather than using a secondary water system. Thermal energy from nuclear reactors can also be used directly, without conversion to electricity. Nuclear reactor heat can be used in hydrogen production and other commercial operations, such as water desalination and the production of petroleum products (extracting oil from tar sands, creating synthetic oil from coal, etc.).
Staffing
Several SMR developers are claiming that their designs will require fewer staff members to run the reactors because of the increased inherent and passive safety systems. Fewer staff members is also a safety risk if plant owners decide to cut corners by assigning even fewer support staff to each reactor. Some of the reactors, like the Toshiba 4S, are reportedly designed to run with little supervision.
Load following
Nuclear power plants have been historically deployed to cover the base load of the electricity demand.
Some nuclear power plants might perform daily load cycling operation (i.e. load following) between 50% and 100% of their rated power. With respect to the insertion of control rods or comparable action to reduce the nuclear power generation, a more efficient alternative might be the “Load Following by Cogeneration”, i.e. diverting the excess of power, respect to the electricity demand, to an auxiliary system. A suitable cogeneration system needs:
- to have a demand of electricity and/or heat in the region of 500 MWe–1.5 GWt;
- to meet a significant market demand;
- to have access to adequate input to process;
- to be flexible: cogeneration might operate at full load during the night when the request of electricity is low, and be turned off during the daytime.
From the economic standpoint, it is essential that the investment in the auxiliary system is profitable. District heating, desalination and hydrogen have been proposed as technically and economically feasible options. SMR can be ideal to do load following being used for desalination over the night.
Waste reduction
Many
SMRs are fast reactors that are designed to have higher fuel burnup
rates, reducing the amount of waste produced. At higher neutron energy
more fission products can be usually tolerated. As mentioned before, some SMRs are also breeder reactors, which not only "burn" fuels like 235
U, but will also convert fertile materials like 238
U (which occurs naturally at a much higher concentration than 235
U) into usable fuels.
Some reactors are designed to run on the alternative thorium fuel cycle, which offers significantly reduced long-term waste radiotoxicity compared to the uranium cycle.
There has been some interest in the concept of a traveling wave reactor, a new type of breeder reactor that uses the fuel it breeds. The idea would eliminate the need to remove the spent fuel and "clean" it before reusing any newly bred fuel.
Safety
Since there are several different ideas for SMRs, there are many different safety features that can be involved. Coolant systems can use natural circulation – convection – so there are no pumps, no moving parts that could break down, and they keep removing decay heat after the reactor shuts down, so that the core doesn't overheat and melt. Negative temperature coefficients in the moderators and the fuels keep the fission reactions under control, causing the fission reactions to slow down as temperature increases. While passive control is a key selling point, a functioning reactor may also need an active cooling system in case the passive system fails. This addition is expected to increase the cost of implementation. Additionally, SMR designs call for weaker containment structures.
Some SMR designs have underground placement of the reactors and spent-fuel storage pools, which provides more security. Smaller reactors would be easier to upgrade quickly, require a permanent workforce, and have better passive quality controls.
Economics
A key driver of SMRs are the alleged improved economies of scale, compared to larger reactors, that stem from the ability to prefabricate them in a manufacturing plant/factory. Yet, according to some studies, the capital cost of SMRs and larger reactors are practically equivalent. A key disadvantage is that the improved affordability can only be realised if the factory is built in the first place, and this is likely to require initial orders for 40–70 units, which some experts think unlikely.
Another economic advantage of SMR is that the initial cost of building a power plant using SMR is much less than that of constructing a much more complex, non-modular, large nuclear plant. This makes SMR a smaller-risk venture for power companies than other nuclear power plants. However, modularisation and modularity influence the economic competitiveness of SMRs. Financial and economic issues can hinder SMR construction.
However operational staffing costs per unit output increase as reactor size decreases, due to some staffing costs being fixed and lesser economies of scale. For example, a similar number of technical and security staff to a large reactor may be required. For small SMRs staff costs per unit output can be as much as 190% higher than the fixed operating cost of large reactors.
In 2017 an Energy Innovation Reform Project study of eight selected companies looked at reactor models with reactor capacity between 47.5 MWe and 1,648 MWe in development. The study found the advanced reactors had an average capital cost total of $3,782/kW, average operating cost total of $21/MWh and levelized cost of electricity of $60/MWh. However there is no standardized approach to evaluate the economic and financial performance of the latest reactors in development, so it’s difficult to make any comparisons between models and existing infrastructure.
Founder of The Energy Impact Center, Bret Kugelmass, believes thousands of SMRs could be built in parallel, "thus reducing costs associated with long borrowing times for prolonged construction schedules and reducing risk premiums currently linked to large projects." Executive Vice President at GE Hitachi Nuclear Energy, Jon Ball, agreed, saying the modular elements of SMRs will also help reduce costs associated with extended construction times.
Licensing
A major barrier is the licensing process, historically developed for large reactors, preventing the simple deployment of several identical units in different countries. In particular the US Nuclear Regulatory Commission process for licensing has focused mainly on large commercial reactors. The design and safety specifications, staffing requirements and licensing fees have all been geared toward reactors with an electrical output of more than 700MWe.
Licensing for SMRs has been an ongoing discussion. There was a workshop in October 2009 about licensing difficulties and another in June 2010, with a US congressional hearing in May 2010. With growing worries about climate change and greenhouse gas emissions, added to problems with hydrocarbon supplies from foreign countries and accidents like the BP oil rig explosion in the Gulf of Mexico, many US government agencies are working to push the development of different licensing for SMRs. However, some argue that weakening safety regulations to push the development of SMRs may cancel out their enhanced safety characteristics.
The U.S. Advanced Reactor Demonstration Program will help license and build two prototype SMRs during the 2020s, with up to $4 billion of government funding support.
Non-proliferation
Nuclear proliferation, or the use of nuclear materials to create weapons, is a concern for small modular reactors. As SMRs have lower generation capacity and are physically small, they are intended to be deployed in many more locations than existing nuclear plants. This means both at more sites in existing nuclear power states, and in more countries that previously did not have nuclear plants. It is also intended that SMR sites have much lower staffing levels than current nuclear plants. Because of the increased number of sites, with fewer staff, physical protection and security becomes an increased challenge which could increase proliferation risks.
Many SMRs are designed to lessen the danger of materials being
stolen or misplaced. Nuclear reactor fuel can be low-enriched uranium,
with a concentration of less than 20% of fissile 235
U.
This low quantity, non-weapons-grade uranium makes the fuel less desirable for weapons production.
Once the fuel has been irradiated,
the fission products mixed with the fissile materials are highly
radioactive and require special handling to remove safely, another
non-proliferation feature.
Some SMR designs are intended to have lifetime cores so the SMRs do not need refuelling. This improves proliferation resistance by not requiring any on-site nuclear fuel handling. But it also means that there will be large inventories of fissile material within the SMRs to sustain a long lifetime, which could make it a more attractive proliferation target. A 200 MWe 30-year core life light water SMR could contain about 2.5 tonnes of plutonium toward the end of its working life.
Light-water reactors designed to run on the thorium fuel cycle offer increased proliferation resistance compared to conventional uranium cycle, though molten salt reactors have a substantial risk.
The modular construction of SMRs is another useful feature. Because the reactor core is often constructed completely inside a central manufacturing facility, fewer people have access to the fuel before and after irradiation.
Reactor designs
Numerous new reactor designs have been proposed across the world. A small selection of the most notable current SMR designs is listed below.
Design Licensing Under construction Operational Cancelled Retired
Name | Gross power (MWe) | Type | Producer | Country | Status |
---|---|---|---|---|---|
4S | 10–50 | SFR | Toshiba | Japan | Detailed design |
ABV-6 | 6–9 | PWR | OKBM Afrikantov | Russia | Detailed design |
ACP100 | 125 | PWR | China National Nuclear Corporation | China | Design complete |
ARC-100 | 100 | SFR | ARC Nuclear | Canada | Design: Vendor design review. One unit approved for construction at Point Lepreau Nuclear Generating Station in December 2019. |
ANGSTREM | 6 | LFR | OKB Gidropress | Russia | Conceptual design |
B&W mPower | 195 | PWR | Babcock & Wilcox | United States | Cancelled in March 2017 |
BANDI-60 | 60 | PWR (floating) | KEPCO | South Korea | Detailed design |
BREST-OD-300 | 300 | LFR | Atomenergoprom | Russia | Under construction |
BWRX-300 | 300 | ABWR | GE Hitachi Nuclear Energy | United States | Licensing stage |
CAREM | 27–30 | PWR | CNEA | Argentina | Under construction |
Copenhagen Atomics Waste Burner | 50 | MSR | Copenhagen Atomics | Denmark | Conceptual design |
CMSR | 100 | MSR | Seaborg Technologies | Denmark | Conceptual design |
EGP-6 | 11 | RBMK | IPPE & Teploelektroproekt Design | Russia | Operating (not actively marketed due to legacy design, will be taken out of operation permanently in 2021) |
ELENA | 0.068 | PWR | Kurchatov Institute | Russia | Conceptual design |
Energy Well | 8.4 | MSR | cs:Centrum výzkumu Řež | Czechia | Conceptual design |
Flexblue | 160 | PWR | Areva TA / DCNS group | France | Conceptual design |
Fuji MSR | 200 | MSR | International Thorium Molten Salt Forum (ITMSF) | Japan | Conceptual design |
GT-MHR | 285 | HTGR | OKBM Afrikantov | Russia | Conceptual design completed |
G4M | 25 | LFR | Gen4 Energy | United States | Conceptual design |
IMSR400 | 185–192 | MSR | Terrestrial Energy | Canada | Conceptual design |
TMSR-500 | 500 | MSR | ThorCon | Indonesia | Conceptual design |
IRIS | 335 | PWR | Westinghouse-led | international | Design (Basic) |
KLT-40S | 35 | PWR | OKBM Afrikantov | Russia | Operating |
MHR-100 | 25–87 | HTGR | OKBM Afrikantov | Russia | Conceptual design |
MHR-T | 205.5x4 | HTGR | OKBM Afrikantov | Russia | Conceptual design |
MRX | 30–100 | PWR | JAERI | Japan | Conceptual design |
NP-300 | 100–300 | PWR | Areva TA | France | Conceptual design |
NuScale | 60 | PWR | NuScale Power LLC | United States | Licensing stage |
Nuward | 300–400 | PWR | consortium | France | Conceptual design, construction anticipated in 2030 |
PBMR-400 | 165 | HTGR | Eskom | South Africa | Cancelled. Postponed indefinitely |
RITM-200 | 50 | PWR | OKBM Afrikantov | Russia | Operational since October 2019 |
Rolls-Royce SMR | 440 | PWR | Rolls-Royce | United Kingdom | Design stage |
SMART | 100 | PWR | KAERI | South Korea | Licensed |
SMR-160 | 160 | PWR | Holtec International | United States | Conceptual design |
SVBR-100[65][66] | 100 | LFR | OKB Gidropress | Russia | Detailed design |
SSR-W | 300–1000 | MSR | Moltex Energy | United Kingdom | Conceptual design |
S-PRISM | 311 | FBR | GE Hitachi Nuclear Energy | United States/Japan | Detailed design |
TerraPower | 10 | TWR | Intellectual Ventures | United States | Conceptual design |
U-Battery | 4 | HTGR | U-Battery consortium[c] | United Kingdom | Design and development work |
VBER-300 | 325 | PWR | OKBM Afrikantov | Russia | Licensing stage |
VK-300 | 250 | BWR | Atomstroyexport | Russia | Detailed design |
VVER-300 | 300 | BWR | OKB Gidropress | Russia | Conceptual design |
Westinghouse SMR | 225 | PWR | Westinghouse Electric Company | United States | Cancelled. Preliminary design completed. |
Xe-100 | 80 | HTGR | X-energy | United States | Conceptual design development |
Updated as of 2014. Some reactors are not included in IAEA Report. Not all IAEA reactors are listed yet. |
Proposed sites
Canada
In 2018, the Canadian province of New Brunswick announced it would invest $10 million to attract SMR research to New Brunswick with a potential site for a demonstration project at the Point Lepreau Nuclear Generating Station. It was later announced that SMR proponents Advanced Reactor Concepts and Moltex would open offices in New Brunswick with the potential of developing sites at Lepreau.
On 1 December 2019, the Premiers of Ontario, New Brunswick and Saskatchewan signed a memorandum of understanding "committing to collaborate on the development and deployment of innovative, versatile and scalable nuclear reactors, known as Small Modular Reactors (SMRs)." They were later joined by Alberta in August 2020.
China
In July 2019 China National Nuclear Corporation announced it would start building a demonstration ACP100 SMR on the north-west side of the existing Changjiang Nuclear Power Plant by the end of the year.
Poland
Polish chemical company Synthos declared plans to deploy a Hitachi BWRX-300 reactor (300 MW) in Poland by 2030. A feasibility study for the project was completed in December 2020 and licensing process started with Polish National Atomic Energy Agency.
United Kingdom
In 2016 it was reported that the UK Government was assessing sites for deploying SMRs in Wales - including the former Trawsfynydd nuclear power station - and on the site of former nuclear or coal-fired power stations in Northern England. Existing nuclear sites including Bradwell, Hartlepool, Heysham, Oldbury, Sizewell, Sellafield and Wylfa are thought to be possibilities. The target cost for a 440 MWe Rolls-Royce SMR unit is £1.8 billion for the fifth unit built. In 2020 it was reported that Rolls-Royce has plans to construct up to 16 SMR's in the UK. In 2019, the company received £18 million to begin designing the modular system, and the BBC claims that the government will provide an additional £200 million for the project as a part of its green plan for economic recovery.
United States
In December 2019 the Tennessee Valley Authority was authorized to receive an Early Site Permit (ESP) by the Nuclear Regulatory Commission for potentially siting an SMR at its Clinch River Site in Tennessee. This ESP will be valid for up to 20 years, and addresses site safety, environmental protection and emergency preparedness associated. TVA has not made a technology selection so this ESP is applicable for any of the light-water reactor SMR designs under development in the United States.
The Utah Associated Municipal Power Systems (UAMPS) announced a teaming partnership with Energy Northwest to explore siting a NuScale Power reactor in Idaho, possibly on the Department of Energy's Idaho National Laboratory.
The Galena Nuclear Power Plant in Galena, Alaska
was a proposed micro nuclear reactor installation intended to reduce
the costs and environmental pollution required to power the town. It was
a potential deployment for the Toshiba 4S reactor.