This booklet is intended to complement the IAEA Advanced Reactor Information System (ARIS), which can be accessed at http://aris.iaea.org. This publication was developed by the Nuclear Power Technology Development Section, Division of Nuclear Power of the IAEA Department of Nuclear Energy, in collaboration with Member States.
INTRODUCTION
Russian Federation Conceptual Design UK SMR 443 PWR Rolls-Royce and Partners United Kingdom Conceptual Design NuScale 12 × 60 PWR NuScale Power Inc. /USA Pre-conceptual design.
Each description includes a general design description and philosophy, target applications, development milestone, nuclear steam supply system, a table of key design parameters, and then descriptions of the reactor core, engineered safety features, plant layout, design and licensing status. The views expressed do not necessarily reflect those of the International Atomic Energy Agency or its member countries and remain the responsibility of the contributors.
For this brochure, an attempt has been made to present all SMR designs within the above categories. This booklet is enriched with a number of annexes that provide Member States readers with various charts and tables to understand the essential technical facts of SMR models.
Some rely heavily on proven technologies to operate large capacity reactors, while others do not use a modular or integral design approach. They are presented in this booklet for the sake of completeness and as designers cater to certain niche markets for their products.
It includes a world map of SMR developers, a general deployment timeline, government and private sectors on a world map of SMR SMR developers, a general deployment timeline, government and private sectors on the development of SMR technology, and an interesting chart that represents the level of planning or deployment of SMRs based on their output capacity.
WATER COOLED
SMALL MODULAR REACTORS (LAND BASED)
Introduction
CAREM is a national SMR development project based on LWR technology, coordinated by the Argentine National Atomic Energy Commission (CNEA) in collaboration with the leading nuclear companies in Argentina, with the aim of developing, planning and building innovative small nuclear power plants with high economic competitiveness and level security. CAREM is an integral type PWR based on an indirect steam cycle with features that simplify the design and support the goal of achieving a higher level of safety.
Target Application
Main Design Features Design Philosophy
CAREM (CNEA, Argentina)
- Safety Features
- Plant Safety and Operational Performances
- Instrumentation and Control Systems
- Plant Layout Arrangement
- Fuel Cycle Approach
- Waste Management and Disposal Plan
- Plant Economics
- Development Milestones
Self-pressure of the primary system in the steam dome is the result of the liquid-steam equilibrium. Due to the self-pressure of the RPV (steam dome), the system keeps the pressure very close to the saturation pressure.
ACP100 (CNNC, China)
Development Milestones
The CSMR is a Generation III+ reactor with a design life of 70 years (extendable to 100 years) and a capacity factor of 90%. CSMR does not require enriched fuel or a fuel qualification program because it relies on natural uranium.
CANDU SMR TM (Candu Energy Inc, Canada)
The CSMR provides large volumes of water that are available to provide cooling of the core in case of accidents, including passive means. The emergency core cooling system supplies emergency coolant to the reactor heads in the event of a loss of coolant accident (LOCA).
CAP200 (SNERDI/SPIC, China)
- Electric Power Systems
- Conventional Island Systems
- Plant Arrangement Reactor building
- Design and Licensing Status Conceptual design finished
The pressure nozzles are used in the case of CAP200 to connect the RPV and SGs replacing main pipes. It functions to (1) control the normal operation of the facility, (2) ensure that critical systems are operating within their designed and licensed limits, and (3) provide control room information and alarms to operators.
DHR400 (CNNC, China)
Plant Layout Arrangement
The reactor building consists of a closed hall and auxiliary buildings including heat supply rooms, storage and treatment rooms for radioactive waste etc. The reactor building is equipped with closed circuit monitoring system to monitor and protect the area.
Design and Licensing Status
Development Milestones
The heating reactor of advanced low pressure and passive safety system – 200 MW(h) (HAPPY200) is a so-called pool-loop combined type reactor, which has both characteristics of swimming pool reactor and PWR to some extent. Aiming for high reliability with inherent safety features, the HAPPY200 can be installed near the targeted heat supply district or community with high population density.
HAPPY200 (SPIC, China)
Design and Licensing Status
The TEPLATOR facility will use already irradiated conventional light water reactor fuel (which has not been burned to its regulatory and design limits). The TEPLATOR is designed for the production of clean district heating energy for cities with 100,000 or more inhabitants.
TEPLATOR TM (UWB Pilsen & CIIRC CTU, Czech Republic)
Safety Features General safety features
The decay heat removal system is integrated as the energy storage system connected to the secondary circuit. The heating/cooling system is located in the heat exchanger hall next to the central TEPLATOR hall.
NUWARD TM (EDF Consortium, France)
The overall size and especially the height of the reactor coolant system is therefore significantly reduced due to the thermal effect of the reactor. The large volume of the pressure apparatus provides margins for the operational transients as well as for the normal operation of the reactor.
IRIS (IRIS International Consortium)
The EHRS provides both the main post-LOCA depressurization of the primary system and the core cooling functions. A specific feature of IRIS is the radial water layer of 1.7 m between the edge of the core and the RV.
DMS (Hitachi-GE Nuclear Energy, Japan)
Plant Layout Arrangement Reactor Building
The PCV compactness is achieved by a drywell in the form of a dish and an eccentric RPV arrangement, i.e. the RPV is installed not in the real center but in an eccentric center of the PVC. The number of equipment is reduced by integrating high and low pressure condensate pumps and optimizing the configuration of systems.
Main Design Features Design Philosophy
IMR uses the Hybrid Heat Transport System (HHTS), a natural circulation system for primary heat transport. The on-board control rod steering mechanism (CRDM) is the primary means of controlling reactivity.
IMR (Mitsubishi Heavy Industries, Japan)
The core is located at the bottom of the RPV and the SGs are located at the top of the RPV. A C-type steam generator is used for the SGV to optimize space utilization in the steam section of the RPV.
SMART (KAERI, Republic of Korea and K.A.CARE, Saudi Arabia)
The braking system consists of the lower braking area (LCA), the upper containment area (UCA), the fuel supply water storage tank (IRWST) and the CPRSS, in addition to these, it includes the CPRSS heat removal system ( CHRS). The off-site power consists of the plant system (SWYD) and the transmission system, and the on-site power consists of the main power system (MP), the auxiliary power system of the plant (AP) and the DC distribution system and the instrument and control system of power (DC/IP) .
RITM-200 (JSC “Afrikantov OKBM”, Russian Federation)
Instrumentation and Control Systems
The land-based small power plant consists of two RITM-200 reactors with a specified electrical power of 100 MW. The optimized design of the small nuclear power plant consists of one reactor building with two RITM-200 reactors.
UNITHERM (NIKIET, Russian Federation)
Plant Layout Arrangement Reactor Building
The detailed design phase includes the qualification of the core, heat exchangers, CEDMs and other components. The design and operation of the VK-50 simplified BWR reactor in the Russian Federation for 50 years is used as the basis for the design of the VK-300 reactor.
VK-300 (NIKIET, Russian Federation)
Instrumentation and Control Systems Instrumentation and Control Systems based
Thanks to new layout concepts for the main equipment of the VK-300 power unit, the control dimensions do not exceed the dimensions of the WWER-1000 reactor. Research and development activities are currently underway to further validate and update the design approach adopted on the VK-300 model.
KARAT-45 (NIKIET, Russian Federation)
The reactor steam removal system is designed to transport the steam generated in the reactor to the turbine. The reactor core is located in the lower part of the reactor and consists of 109 fuel assemblies (FA).
KARAT-100 (NIKIET, Russian Federation)
The steam exhaust system is designed to remove steam from the reactor directly to the turbine plant. The designers also claim that the overall size of the steam generating unit allows the reactor to be transported by rail.
RUTA-70 (NIKIET, Russian Federation)
The reactor core is located in the lower part of the reactor vessel, the vault, in the envelope of the chimney part. The distribution head is located in the upper part of the casing of the chimney part.
ELENA (NRC “Kurchatov Institute”, Russian Federation)
Development Milestones Not determined
The UK SMR has been developed to provide a market-driven, affordable, low-carbon power generation capability. The UK SMR is primarily intended to supply base load electricity both on the coast and inland.
UK SMR (Rolls-Royce and Partners, United Kingdom)
Plant Layout
The reactor coolant system (RCS) is a subsystem of the NPM that provides primary coolant circulation relying on natural circulation. The main control room is located below the classroom in the control building adjacent to the reactor building.
BWRX-300 (GE-Hitachi Nuclear Energy, USA and Hitachi-GE Nuclear Energy, Japan)
- Electrical Systems
- Instrumentation and Control Systems
- Plant Layout Arrangement
- Design and Licensing Status
- Fuel Cycle Approach
- Waste Management and Disposal Plan
The RPV and chimney height are optimally matched to the thermal efficiency and natural circulation of the BWRX-300. The BWRX-300 uses natural circulation modeling and operational information from the ESBWR and the Dodewaard BWR in the Netherlands.
SMR-160 (Holtec International, United States of America)
Plant Layout Arrangement Containment Enclosure Structure
The SMR-160 reactor is housed in a containment structure (CS) protected by an enclosing structure (CES). High-level waste management and disposal for the SMR-160 uniquely benefits from the integration of Holtec International's dry storage technologies.
Westinghouse SMR (Westinghouse Electric Company LLC, United States of America)
Development Milestones
The mPower design can be retrofitted to support other heat-demanding industries, desalination or cogeneration applications. The mPower design is based on the use of systems and components with an advanced factory architecture that reduces licensing and construction risks.
The large reactor coolant system (RCS) volume in the mPower reactor allows more time for safety systems to react in the event of an accident. The mPower design includes analog circuitry to remove heat from the secondary and from the containment systems.
SMALL MODULAR REACTORS (MARINE BASED)
The KLT-40S is a PWR developed for a floating nuclear power plant (FNPP) with a capacity of 35 MW(e) per module. The FNPP with a KLT-40S reactor can be manufactured in shipyards and delivered to the sites fully assembled, tested and ready for use.
KLT-40S (JSC “Afrikantov OKBM”, Russian Federation)
Electric Power Systems
The electrical system in FPU consists of: the main electrical system; and emergency electrical system. The FNPP keel carrying the KLT-40S, Akademik Lomonosov in the Chukotka region, was laid down in 2007.
RITM-200M (JSC “Afrikantov OKBM”, Russian Federation)
- Plant Safety and Operational Characteristics The main characteristics are
- Monitor and Control Systems
- General Layout of the Plant The Optimized Floating Power
- Approach to the Fuel Cycle
- Waste Management System and Waste Disposal Plan
- Design State and Licensing Status
The RITM series reactors are the evolutionary development of the reactors (OK-150, OK-900 and KLT-40 series) for Russian nuclear icebreakers with a total operating experience of more than 60 years (more than 400 reactor years). The configuration of the steam generating cassettes allows them to be installed compactly in the RPV.
ACPR50S (CGNPC, China)
For non-LOCA events, the SHR removes the decomposition heat from the core through natural circulation between the OTSG and the SHR heat exchanger. The compact control room is designed for one-man operation under normal conditions on the plant and is located in the ship (offshore).
ABV-6E (JSC “Afrikantov OKBM”, Russian Federation)
Counter-current circulation is used, that is, the refrigerant of the primary circuit in the intertube space moves downwards, while the refrigerant of the secondary circuit moves upward in the pipes. Reduction of construction time is achieved due to the compact design of the reactor system.
VBER-300 (JSC “Afrikantov OKBM”, Russian Federation)
Fuel Cycle Approach
The VBER-300 design concept allows a flexible fuel cycle for the reactor core with standard VVER FAs. 2007-2009 Technical task for NPP design and final design of the reactor plant, automated process control system and heat generating plant; feasibility, economic and investment studies of VBER-300 RP NPP for Mangistau region, Kazakhstan.
SHELF (NIKIET, Russian Federation)
ACS;
ECCS;
Emergency reduction of primary coolant loss is provided passively by draining water from the emergency cooling tanks into the reactor due to gravity due to the difference in altitude between the tank and the reactor. The duration of the operational reactor core is 6 years (8 years for the updated version of SHELF-M).
HIGH TEMPERATURE GAS COOLED
SMALL MODULAR REACTORS
The first concrete of the HTR-PM demonstration plant was poured on December 9, 2012 in Rongcheng, Shandong Province. Civil works on the nuclear island buildings were completed in 2016 and the first of two reactor pressure vessels was installed in March 2016.
HTR-PM (Tsinghua University, China)
The primary pressure boundary consists of the reactor pressure vessel (RPV), the steam generator pressure vessel (SGPV) and the hot gas duct pressure vessel (HDPV), all of which are housed in a containment cavity. the concrete. The HTR-PM is designed with the following safety features: (1) the radioactive inventory in the helium primary coolant is very small during normal operating conditions and, even if released, no emergency measures need to be taken; (2) for any reactivity accident or loss of coolant accident, raising fuel elements.
STARCORE (StarCore Nuclear, Canada, United Kingdom and United States)
- Target Applications
- Plant Safety and Operational Performance
- Waste Management and Disposal Plan
- Development Milestones
The plants also have 69 KV 100 km HVDC transmission lines which are included in the cost of the plant. There are automatic bi-stable valves at the inlet and outlet, which seal off the core in the event of pressure loss.
GTHTR300 (JAEA Consortium, Japan)
Plant Safety and Operational Performance
The reactor module is fixed in the horizontal direction, while gas turbine and heat exchanger modules can move due to thermal expansion in the direction. Because the reactor unit can produce high coolant outlet temperatures, the modular helium reactor system can also efficiently produce hydrogen, e.g.
GT-MHR (JSC “Afrikantov OKBM”, Russian Federation)
Plant Layout Arrangement The plant layout is shown on the right
Facilities for long-term storage of spent nuclear fuel (SNF) and solid/solid radioactive waste (RW) are included in the complex of a commercial NPP with 4 GT-MHR units. 1998 GT-MHR becomes an option within US/RF Pu disposition strategy 1999 Conceptual design review by international expert group.
MHR-T Reactor (JSC “Afrikantov OKBM”, Russian Federation)
Plant Arrangement
The main components of each NPP module are arranged in isolated premises of the underground containment of the NPP main building. The chemical technology sector equipment is arranged outside the containment of the core building's main building.
MHR-100 (JSC “Afrikantov OKBM”, Russian Federation)
Specific Design Features Design Philosophy
In LOCA condition with failures of all active circulation systems and power sources, the operational safety limit of the fuel is not exceeded. In addition to the inherent features, the MHR-100 incorporates safety systems based on: (i) Simplicity of both system operation algorithm and design; (ii) Natural processes for safety system operation under accident conditions; (iii) Redundancy, physical separation and independence of systems; (iv) Stability of the internal and external impacts and malfunctions caused by accident conditions; (v) Continuous or periodic diagnostics of system conditions; (vi) Conservative approach used in the design, applied to the list of initiating events, to accident scenarios, and to the selection of the definitive parameters and design margins.
Instrumentation and Control
Preconditions and conditions that exclude RPV brittle fracture include keeping the fast neutron fluence and the RPV temperature below permissible limits. The high heat storage capacity of the reactor core and the high acceptable temperatures of fuel and graphite enable passive shutdown cooling of the reactor in the event of accidents, including LOCA (heat removal from the reactor vessel by radiation, conduction and convection), while keeping the fuel and core temperatures within acceptable limits Design MHR- 100 does not envisage specific active safety systems.
Design Variants and Plant Arrangements Based on the Modular MHR-100
This decision limits the release of radioactivity in the network circuit and ensures the radiological purity of the process product and minimal contamination of the primary circuit with process impurities. Feasibility study of the application of the MHR-100-SMR plant for large-scale hydrogen production, technical and economic evaluation of the potential of the plant to supply hydrogen to the expected market.
PBMR ® -400 (PBMR SOC Ltd, South Africa)
Fresh fuel elements are added to the top of the reactor while used fuel pebbles are removed from the bottom to keep the reactor at full power. The main barriers to the release of fission products are the coatings of the fuel particles.
AHTR-100 (Eskom Holdings SOC Ltd., South Africa)
As in the PBMR®, the AHTR-100 is a high-temperature helium-cooled, graphite-moderated pebble-bed reactor, but with a refueling scheme. As in PBMR®, AHTR-100 safety does not rely on engineered systems that can fail, but on inherent design and the laws of physics.
HTMR100 (STL Nuclear (Pty) Ltd., South Africa)
A fuel qualification and testing program will be conducted on the fuel before loading the reactor. All parts of the internal core are designed for the life of the reactor.
Xe-100 (X Energy, LLC, United States of America)
The pebbles are then removed from the reactor and transferred to the spent fuel storage system. The FHS is a closed system that allows for 100% accountability of the fuel as it enters and exits the reactor.
SC-HTGR (Framatome Inc., United States of America)
The safety profile of the SC-HTGR allows it to be co-located with industrial facilities that use high temperature steam. The reactor vessel is part of the vessel system, which is and also the primary pressure-containing components.
HTR-10 (Tsinghua University, China)
Design and Licensing Status HTR-10 is operational
Waste Management and Disposal Plan To be included in the national plan of test facilities
Research and Development Plan
JAEA performed long-term high-temperature operation (950°C/50 days of operation) to demonstrate the high-temperature heat supply capability. The objectives of the HTTR are to: (i) establish and upgrade the technological basis for the advanced HTGR; (ii) Conduct innovative basic research in high temperature engineering; and (iii) demonstrate high-temperature heat applications and utilization obtained from nuclear heat.
HTTR (JAEA, Japan)
Future plans
Following the restart of the HTTR, a number of activities are planned to be carried out including safety demonstration tests in the OECD/NEA LOFC project, discussions on technology demonstration tests of the heat utilization system consisting of helium gas turbines and production facilities of hydrogen to be bonded. for HTTR, operational test of fuel performance and international cooperation and development of human resources using HTTR. As the HTTR can be used as a test bed for international cooperation, JAEA plans to launch new international projects based on the operation of the HTTR and welcomes discussion with potential partners.
