IAEA International Atomic Energy Agency
Advances in Development and Deployment of
Small Modular Reactor Design and Technology
Dr. M. Hadid Subki
Nuclear Power Technology Development Section
Division of Nuclear Power, Department of Nuclear Energy
ANNuR – IAEA – U.S.NRC Workshop on
Small Modular Reactor Safety and Licensing 12 – 15 January 2016, Vienna, Austria, M Building OE Press Room
IAEA
Outline
Motivation, driving forces, & definition
SMRs for immediate & near term deployment
SMR estimated time of deployment
SMR design characteristics
Perceived advantages and potential challenges
Key Member States activity in SMR design development
Elements to Facilitate SMR Deployments
www.iaea.org/NuclearPower/Technology/
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Part I
Introduction to SMR Design and
Technology Development
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SMRs are not new for IAEA Member States
1958 – 1962:
Small: Power ≤ 100 MWe
Medium: Power ≤ 150 MWe
1963 – 1971:
Small: Power ≤ 100 MWe
Medium: Power ≤ 500 MWe
~ 1985:
Small: Power ≤ 100 MWe
Medium: Power ≤ 500 MWe
Designation of the power-range changes over the decades
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SMRs are not new for IAEA Member States
1996 – 2012: • Small: Power ≤ 300 MWe
• Medium: 300 < P ≤ 700 MWe
• Started R&D for Advanced
modular reactors ▲ ▲ ▲
• Floating Nuclear Power Plants
1989 – 1995:
Small: Power ≤ 300 MWe
Medium: 300 < P ≤ 700 MWe
Including: AP600, SBWR,
CANDU3 and CANDU6
2012 – 2017:
• Small: Power ≤ 300 MWe
• Medium: 300 < P ≤ 700 MWe
• Modular reactor – trend of development
• HTGR SMR under construction in China
• iPWR SMR under construction in
Argentina
• Some certified, many under licensing
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Past Activities Relevant to SMR Regulatory Issues
No. Technical Meetings (TM) Place, Dates
1 The 6th INPRO Dialogue Forum on Global Nuclear
Energy Sustainability: Licensing and Safety Issues for SMRs
• IAEA, Vienna, Austria
• 29 July – 2 Aug 2013
2 TM on Environmental Impact Assessment for the
Deployment of SMRs
• IAEA, Vienna, Austria
• 28 – 31 October 2013
3 TC Interregional Workshop on Design, Technology and
Deployment Considerations for SMRs
• IAEA, Vienna, Austria
• 2 – 5 June 2014
6
Publications: Booklets, Technical Reports, Nuclear Energy Series, TECDOCs
In-House Collaboration Enhances Productivity and Quality
in Serving the Member States
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Motivation – Driving Forces…
7
The need for flexible power generation for wider range of
users and applications
Replacement of aging fossil-fired units
Cogeneration needs in remote and off-grid areas
Potential for enhanced safety margin through inherent and/or
passive safety features
Economic consideration – better affordability
Potential for innovative energy systems: • Cogeneration & non-electric applications
• Hybrid energy systems of nuclear with renewables
Advanced Reactors that produce electric power up to 300 MW, built in
factories and transported as modules to utilities and sites
for installation as demand arises.
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SMR Technology Development
USA
mPower
NuScale
W - SMR
SMR - 160
EM 2
GT - MHR
PRISM
G 4 M
CANADA
ARGENTINA
CAREM - 25
CHINA
HTR-PM
INDIA
PFBR - 500
AHWR - 300
PHWRs
ITALY
IRIS
SOUTH AFRICA
PBMR
FRANCE
Flexblue JAPAN
DMS
KOREA
SMART
RUSSIA
StarCore Nuclear
HTMR-100
ACP-100
CEFR
IMR 4S
MHRs RUTA-70
VK-300
KLT-40S ELENA
SVBR-100
BREST300-OD
VBER-300 RITM-200
VVER-300 ABV6-M
UNITERM
SHELF
URANUS
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SMRs for immediate & near term deployment Samples for land-based SMRs
Water cooled SMRs Gas cooled SMRs Liquid metal cooled SMRs
• Land-based, marine-based, and factory fuelled transportable SMRs
• Estimated power limit to be modular/transportable ≤ 180 MW(e)
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11 IAEA Member States with SMRs
(11) United States
NuScale 50 x 12
mPower 180 x 2
W-SMR 225
SMR-160 120
PRISM 311
EM2 240
GT-MHR 285
(9) Russia
KLT-40S 35 x 2
RITM-200 50
ABV-6M 6 x 2
VBER-300 300
VVER-300 311
BREST 300
SVBR 100
(2) China
CEFR 20
HTR-PM 211
ACP100 100
CAP150 150
CAP-F 200(t)
(5) India
PFBR500 500
AHWR300 300
(1) Argentina
CAREM25 27
(3) France
Flexblue 165
(6) Italy
IRIS 325
(7) Japan
4S 30
GTHTR300 300
DMS 300
IMR 350
(8) South Korea
SMART 100
(10) South Africa
PBMR400 400(th)
HTMR-100 100
(4) Germany
IHTR-10 (experimental)
10
MW(th)
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SMRs Under Construction for Immediate
Deployment – the front runners …
Country Reactor
Model
Output
(MWe)
Designer Number
of units
Site, Plant ID,
and unit #
Commercial
Start
Argentina CAREM-25 27 CNEA 1 Near the Atucha-2 site 2017 ~ 2018
China HTR-PM 250 Tsinghua
Univ./Harbin
2 mods,
1 turbine
Shidaowan unit-1 2017 ~ 2018
Russian
Federation
KLT-40S
(ship-borne)
70 OKBM
Afrikantov
2
modules
Akademik Lomonosov units 1 & 2 2016~2017
RITM-200
(Icebreaker)
50 OKBM
Afrikantov
2
modules
RITM-200 nuclear-propelled
icebreaker ship
2017 ~ 2018
CAREM-25 HTR-PM KLT-40S
Page 11 of 37
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SMRs under development for Near-term Deployment - Some samples …
Name Design
Organization Country of
Origin
Electrical Capacity,
MWe Design Status
1 System Integrated Modular Advanced Reactor (SMART)
Korea Atomic Energy Research Institute
Republic of Korea 100 Standard Design Approval
Received 4 July 2012
2 mPower B&W
Generation mPower United States of
America 180/module
Preparing for Design Certification Application
3 NuScale NuScale Power Inc. United States of
America 50/module
(gross) Preparing for Design
Certification Application
4 ACP100 CNNC/NPIC China 100 Detailed Design,
Construction Starts in 2016
SMART
mPower NuScale ACP100
Page 12 of 37
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SMRs “Estimated” Timeline of Deployment
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SMART
SMR Design Characteristics (1): iPWR
14
pumps
CRDM
Steam
generators
pressurizer
pumps
core + vessel
core + vessel
CRDM
Steam
generators
Westinghouse
SMR
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SMR Design Characteristics (2)
• Multi modules configuration
• Two or more modules located in one location/reactor building and
controlled by single control room
• reduced staff
• new approach for I&C system
Page 15 of 37
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SMR Design Characteristics (3)
• Modularization (construction technology) • Factory manufactured, tested and Q.A.
• Heavy truck, rail, and barge shipping
• Faster construction
• Incremental increase of capacity addition as needed
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SMR Design Characteristics (Summary)
Integrated
Reactor Coolant System
Multi Modules &
Modular Construction
Passive Engineered
Safety Features
Advanced Instrumentations & Controls
Longer Fuel Cycle
Simplified, compact and
less weight
Enhanced Safety
Performance
Enhanced Maintainability
Better Radiation Control
Extended Design Life
Safer,
Flexible and
Efficient
Operation
Increased
Safety and
Reliability
Better cost
affordability
Main Features Expected Advantage
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SMR Site Specific Considerations
• Site size requirements, boundary conditions, population,
neighbours and environs
• Site structure plan; single or multi-unit site requirements
What site specific issues could affect the site
preparation schedule and costs?
What is the footprint of the major facilities on
the site?
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Advantages Challenges
Te
ch
no
log
y I
ss
ue
s • Shorter construction period
(modularization)
• Potential for enhanced safety and
reliability
• Design simplicity
• Suitability for non-electric
application (desalination, etc.).
• Replacement for aging fossil
plants, reducing GHG emissions
• Licensability (first-of-a-kind
structure, systems and components)
• Non-LWR technologies
• Operability and Maintainability
• Staffing for multi-module plant;
Human factor engineering;
• Post Fukushima action items on
design, safety and licensing
• Advanced R&D needs
No
n-T
ec
hn
o Is
su
es
• Fitness for smaller electricity grids
• Options to match demand growth
by incremental capacity increase
• Site flexibility Smaller footprint
• Reduced emergency planning zone
• Lower upfront capital cost (better
affordability)
• Easier financing scheme
• Economic competitiveness
• Plant cost estimate
• Regulatory infrastructure
• Availability of design for newcomers
• Post Fukushima action items on
institutional issues and public
acceptance
Perceived Advantages & Potential Challenges
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Key Design Characteristics of
Advanced Passive Water-Cooled Reactors Independent of AC Power
• Require no AC power to actuate
/operate Engineered Safety
Features;
• Only gravity flow, condensation
natural circulation forces needed
to safely cool the reactor core
• Passively safe shutdown the
reactor, cools the core, and
removes decay heat out of
containment
1 Less reliance on operator action
Provides 3 to more than 7 days of reactor cooling
without AC power or operator action
2
Incorporating lessons-learned from the
Fukushima Dai-ichi nuclear accident
• Enhanced robustness to extreme external events
by addressing potential vulnerabilities
• Alternate AC independent water additions in
Accident Management – SBO mitigation
• Ambient air as alternate Ultimate Heat Sink
• Filtered containment venting
• Diversity in Emergency Core Cooling System Design simplification
• Fewer number of plant systems
and components
• Reducing plant construction and
O&M costs
3
4
Images Courtesy of Westinghouse and GE Nuclear Energy
20
Page 20 of 37
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• Hydrogen control for DBA & severe accidents
• Filtered venting system
• Enhanced instrumentation and monitoring
system for DBA & severe accidents
• Diversity in spent fuel cooling (reliability)
• Effective use of PSA
• Emergency preparedness and response
• Assure safety on multiple reactors or modules plant
• Diversity in emergency core cooling systems
following loss of all AC power onsite
• Ensure diversity in depressurization means for high
pressure transient
• Confirm independence in reactor trip and ECCS for
sensors, power supplies and actuation systems.
Incorporating Lessons Learned from Major Accidents to
Advanced Reactor and SMR Developments
Resilience towards Extreme external events (regions and sites specific)
Page 21 of 37
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Part II
Technical Description of some
Near Term Deployable SMR Designs
1. Korea – SMART
2. Argentina - CAREM25
3. USA - NuScale
4. USA - mPower
5. China - HTR-PM
6. China - ACP100
7. Russia - KLT-40S
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Republic of Korea: SMART
• Full name: System-Integrated Modular
Advanced Reactor
• Designer: Korea Atomic Energy Research
Institute (KAERI), Republic of Korea
• Reactor type: Integral PWR
• Coolant/Moderator: Light Water
• Neutron Spectrum: Thermal Neutrons
• Thermal/Electrical Capacity:
330 MW(t) / 100 MW(e)
• Fuel Cycle: 36 months
• Salient Features: Passive decay heat
removal system in the secondary side;
horizontally mounted RCPs; intended for sea
water desalination
• Design status: Standard Design Approval
received on 4 July 2012; now under pre-
project engineering with Saudi Arabia
© 2011 KAERI – Republic of Korea
Reproduced courtesy of KAERI
IAEA
SMART - Basic Plant Parameters Thermal Capacity (MW) 330
Electricity Output (MW) 100 (or 90 for combined electricity
generation and desalination)
Expected Capacity Factor (%) ˃ 95
Primary System Pressure (MPa) 15
Core Outlet Temperature (°C) 323
Core Inlet Temperature (°C) 295.7
Steam pressure (MPa) 5.2
Steam temperature (°C) 298 (3°C above saturation temperature)
Refueling Interval (months) 36
Fuel Assembly 17 x 17
Number of Fuel Assembly 57
Active Fuel Length (m) 2
Fuel Enrichment (UO2) < 5%
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SMART (1)
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SMART (2)
SMART - Plant Systems
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SMART - Safety Features
• Passive Residual
Heat Removal
System: 4x50% train
• Safety Injection
System (SIS)
• Shutdown Cooling
System (SCS)
• Reactor Shutdown
System
• Containment Spray
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SMART Design, Licensing and Deployment
• 1999 Conceptual Design Development
• 2002 Basic Design approval (PSA)
• 2012 Standard Design Approval (SDA)
• In March 2015 KAERI signed an agreement with Saudi Arabia’s King Abdullah City for Atomic and Renewable Energy (KA-CARE) to assess the potential for building SMART reactors in the country
• KAERI plans to build a 90 MWe demonstration plant to operate from 2017
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Argentina: CAREM-25
• Full name: Central Argentina de Elementos
Modulares
• Designer: National Atomic Energy
Commission of Argentina (CNEA)
• Reactor type: Integral PWR
• Coolant/Moderator: Light Water
• Neutron Spectrum: Thermal Neutrons
• Thermal/Electrical Capacity: 100.0 MW(t) /
31 MW(e) Gross
• Pressure/Temp: 12.25 MPa / 326oC
• Fuel Cycle: 14 months
• Salient Features: primary coolant system
within the RPV, self-pressurized and relying
entirely on natural convection.
• Design status: Construction started in 2012,
aim for commissioning in October 2018 Reproduced courtesy of CNEA
IAEA
(1) CAREM - Basic Plant Parameters
Thermal Capacity (MW) 100
Electricity Output (MW) 31
Expected Capacity Factor (%) ˃ 90
Primary System Pressure (MPa) 12.25
Core Outlet Temperature (°C) 326
Core Inlet Temperature (°C) 284
Refueling Interval (months) 14
Fuel Assembly (hexagonal ) 108 of 127 position for fuel rods
Number of Fuel Assembly 61
Active Fuel Length (m) 1.4
Fuel Enrichment 3.1
RPV Height (m) 11
RPV Diameter (m) 3.2
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(2) CAREM25
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(3) CAREM25
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CAREM - Safety Features
• Residual heat removal
system (3)
• Reactor shutdown
systems (1, 2)
• Safety Injection
System (4)
• RPV safety relief
valves
• Containment (6)
• Pressure suppression
pool (5)
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CAREM – Safety Features
• Decay Heat Removal
System
• Provide decay heat
removal when SG
feedwater is lost
• Depressurize the
RPV to allow the
Safety Injection
System to function
• Four trains, each of
50% capacity
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CAREM - Safety Features
• Safety Injection
System
• Flood the core in
the event of a loss
of coolant accident
• Two accumulator
of 100% capacity
• Safety Valves
• Provide RPV
overpressure
protection
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CAREM - Safety Features
• Containment
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CAREM - Safety Features
First Shutdown System (FSS) Second Shutdown System (SSS)
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Design, Licensing and Deployment
• Being built next to Atucha
• CAREM concept developed in 1984
• CNEA submitted the PSAR for CAREM-25 in 2009 to ARN
• The licensing process for the construction of CAREM-25 prototype was approved by the Argentina Regulatory Body (ARN) in 2010
• Formal start of construction on February 8, 2014
• First fuel load expected in 2018
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United States of America: NuScale
• Full name: NuScale
• Designer: NuScale Power Inc., USA
• Reactor type: Integral Pressurized Water
Reactor
• Coolant/Moderator: Light Water
• Neutron Spectrum: Thermal Neutrons
• Thermal/Electrical Capacity:
165 MW(t)/45 MW(e)
• Modules per plant: (1 – 12) modules
• Fuel Cycle: 24 months
• Salient Features: Natural circulation cooled;
Decay heat removal using containment; built
below ground
• Design status: Design Certification
application in 4th Quarter of 2016
Reproduced courtesy of NuScale Power
IAEA
NuScale - Basic Plant Parameters
Thermal Capacity (MW) 160
Electricity Output (MW) - Gross 50
Expected Capacity Factor > 95%
Thermal Efficiency ~ 30%
Primary System Pressure (MPa) 12.9
SG Steam (MPa) 3.1
Refueling Intervals 24 months
Fuel Assembly 17x17 PWR Enriched UO2 Fuel with
Zircaloy Cladding
Number of Fuel Assembly 37
Active Fuel Length (m) 2
Fuel Enrichment < 4.95%
RPV Height (m) 17.6
RPV Diameter (m) 2.74 (ID)
Containment Vessel Height (m) 23.165
Containment Diameter (m) 4.572 (OD)
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NuScale (1)
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NuScale (2)
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NuScale (3) Plant Layout Arrangement
• A 12-module plant
(540 MWe) can be
built in two
increments:
• Modules 1-6
• Modules 7-12
(NuScale Power – Safe, Economic, Scalable, Proven Nuclear Technology, Bruce Landrey, August 2012)
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NuScale (4) Nuclear Steam Supply System
Housed in the RPV:
• Reactor core
• Pressurizer
• Steam generators
• Natural circulation
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Safety Features of NuScale
• Containment Vessel
• Decay Heat Removal System
• Emergency Core Cooling System
• Reactor Pool
• Others, i.e., RTS, ESFAS, Control Room
Habitability System
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Safety Features of NuScale
• Containment Vessel
• 15 feet in diameter, 76 feet tall
• Housing the RPV, CRDMs, and
other NSSS piping and
containment
• Designed to accommodate
design basis conditions
• Containment of radioactive
releases following postulated
accidents
• Protecting RPV from external
hazards
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Safety Features of NuScale
• Decay Heat Removal System • Providing core decay heat
removal when the normal decay heat removal is not available
• Two 100% redundant trains of passive design, each consisting of a condenser immersing in the reactor pool, one SG, and associated piping and valves
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Safety Features of NuScale
• Emergency Core Cooling System • Mitigating loss of
coolant accidents
• Providing a defense-in-depth decay heat removal
• Reactor Pool Providing core cooling for a minimum of 72 hours following any design basis accident
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Design, Licensing and Deployment
• Concept conceived in Oregon State University
• OSU granted NuScale Power exclusive rights to the nuclear power plant design in 2007
• In December 2013 USDOE announced its funding support
• Currently in the pre-application review phase with NRC
• NuScale expects to submit its DC application late in 2016
• Western Initiative for Nuclear project
IAEA
• Full name: mPower
• Designer: B&W mPower Generation, United
States of America
• Reactor type: Integral Pressurized Water
Reactor
• Coolant/Moderator: Light Water
• Neutron Spectrum: Thermal Neutrons
• Thermal/Electrical Capacity:
530 MW(t) / 180 MW(e)
• Modules per plant: (1 – 4) modules
• Fuel Cycle: 48-month or more
• Salient Features: integral NSSS, CRDM
inside reactor vessel; Passive safety that
does not require emergency diesel generator
• Design status: Design Certification
application is being rescheduled
United States of America: mPower
Reproduced courtesy of B&W mPower Generation, LLC
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mPower – 1
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mPower – 2
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• Full name: Modular High Temperature
Gas Cooled Reactor – Pebble Bed
Module
• Designer: Tsinghua University, Peoples
Republic of China
• Fuel: TRISO (UO2) with 8.9% enrichment
of fresh fuel element
• Thermal/Electric capacity: 500 MW(t) /
211 MW(e)
• Fuel Cycle: design burn-up to reach
100GWd/t to reduce fuel cycle cost
• Salient Features: high operating
temperature; multiple-module reactors
coupled to one high pressure super-
heated steam turbine generator, sharing
common auxiliary systems
• Design status: 2 modules under
construction for commissioning in 2017
China: HTR-PM
Reproduced courtesy of INET
IAEA
HTR-PM: Overview and Safety Features
• Commercial demonstration unit for electricity production
• Two HTGRs (2x250 MWt) and one turbine-generator unit
(210 MWe)
• Based on HTR-10
• Inherent safety characteristics: • Lower power density
• Coated fuel particles
• Large negative temperature coefficient
• Low excess reactivity (on-line refuelling)
• Passive decay heat removal
• Overall negative reactivity coefficient
• Containment of radioactivity
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HTR-PM: Basic Plant Parameters
Reactor Thermal Capacity (MW) 2 x 250
Electricity Output (MW) 210
Expected Capacity Factor 85
Thermal Efficiency 40%
Primary System Pressure (MPa) 7
Core Inlet/Outlet Temperatures (°C) 250/750
Steam Pressure (MPa) 13.24 (turbine inlet)
Steam Temperature (°C) 566 (turbine inlet)
Refueling Intervals Online refueling
Fuel Type/Assembly Array Pebble bed with coated particle fuel
Fuel Pebble Diameter (cm) 6
Number of Fuel Spheres 420,000
Fuel Enrichment (%) 8.5
Diameter of the Active Core (m) 3
Effective Height of the Active Core (m) 10
RPV Diameter (m) 5.7 (inner)
RPV Height (m) 25
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Nuclear Steam
Supply System
• The Primary Circuit
• Reactor vessel
• Steam generator
• The hot gas duct vessel
• Main helium blower
• The reactor core
• Reactivity control
systems
Status report 96 - HTR-PM
IAEA, 2011
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Fuel Elements
• Fuel element,
spherical
• Outer graphite layer
• Graphite matrix
• Fuel particles
• Coatings
• Fuel Kernel
• Design temperature
1620°C
Advances in Small Modular Reactor Technology Developments, IAEA, 2014
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HTR-PM: Safety Features
• Inherent safety characteristics
• Lower power density
• Coated fuel particles
• Large negative temperature coefficient
• Low excess reactivity (on-line refuelling)
• Passive decay heat removal
• Overall negative reactivity coefficient
• Containment of radioactivity
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HTR-PM Licensing and Deployment
• 1995 Construction of HTR-10 started
• 2000 HTR-10 achieved first criticality
• 2003 HTR-10 full power operation
• 2004 HTR-PM standard design was started
• 2006 Project approved as national key technology project
• 2006 Huaneng Shandong Shidaowan Nuclear Power Co., Ltd, the owner of the HTR-PM, was established
• 2008 HTR-PM Basic design completed
• 2009 Revie of HTR-PM PSAR completed
• 2012 HTR-PM First Pour of Concrete
• 2013 Fuel plant construction completed with installation of equipment on-going
• 2018 First operation expected
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China: ACP100
• Full name: Advanced China PWR 100
• Designer: Nuclear Power Institute of China,
China National Nuclear Corporation (CNNC)
• Reactor type: Integral PWR
• Coolant/Moderator: light water
• Neutron Spectrum: Thermal Neutrons
• Thermal/Electrical Capacity: 385MW(t) /
120 MW(e)
• Fuel Cycle: 24 months
• Salient Features: Underground layout of
reactor building- enhanced protection against
external hazards; Containment vessel
installed in water pool; fully passive safety
facilities.
• Design status: Currently undertaking IAEA
Generic Design Review since April 2015 Reproduced courtesy of CNNC
IAEA
Main design parameters
Thermal power 310MWt
Electrical power ~100MWe
Design life 60 years
Refueling period 2 years
Coolant inlet temperature 282 ℃
Coolant outlet temperature 323 ℃
Coolant average temperature 303 ℃
Best estimate flow 6500 m3/h
Operation pressure 15MPaa
Fuel assembly type CF2 shortened assembly
Fuel active section height 2150 ㎜
Fuel assembly number 57
ACP100 Technical Aspects
ACP100
IAEA
• Primary system and equipment integrated layout. The
maximal size of the conjunction pipe is 5-8 cm, whereas
the large PWR is 80-90cm;
• Large primary coolant inventory;
• Small radioactivity storage quantity. Total radioactivity of
SMR is 1/10 of large PWR’s, meanwhile multi-layer
barrier is added to keep the accident source-term at a
low level;
• Vessel and equipment layout is benefit for natural
circulation.
Technical Aspects Main characteristics
IAEA
• Assurance decay heat removal more effectively. 2-4
times of the efficiency of large PWR heat removal from
the vessel surface;
• Smaller decay thermal power. 1/5-1/10 times of decay
thermal power comparing that of large PWR after
shutdown, and easier to achieve safety by the way of
“passive”;
• Reactor and spent fuel pool lay under the ground level for
better against exterior accident and good for the
reduction of radioactive material release.
Main characteristics (continued)
Technical Aspects
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Russian Federation: KLT-40S
• Designer: OKBM Afrikantov – Russian
Federation
• Reactor type: PWR – Floating Nuclear
Cogeneration Plant
• Coolant/Moderator: H20
• Neutron Spectrum: Thermal Neutrons
• Thermal/Electric capacity: 150 MW(t) /
35 MW(e)
• Fuel Cycle: Single-Loading of LEU fuel
with initial uranium enrichment <20% to
enhance proliferation resistance
• Salient Features: based on long-term
experience of nuclear icebreakers;
cogeneration options for district heating
and desalination
• Design status: 2 units finalizing
construction aims for completion in Q4 of
2016
Reproduced courtesy of OKBM Afrikantov
IAEA
KLT-40S - Overview
(Source: http://www.uxc.com) A floating power unit (FPU) of 2 KLT-40S modules for
cogeneration, 4-loop, 150 MWth or 35 MWe per module
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KLT40S- Basic Plant Parameters Thermal Capacity (MW) 150
Electricity Output (MW) 35
Expected Capacity Factor (%) 70
Thermal efficiency (%) 23.3
Primary System Pressure (MPa) 12.7
Core Outlet Temperature (°C) 316
Core Inlet Temperature (°C) 280
Stem pressure (MPa) 3.82
Steam temperature (°C) 290
Refueling Interval (months) 28
Fuel Assembly Canned, hexahedral
Number of Fuel Assembly 121
Active Fuel Length (m) 1.2
Fuel Enrichment (%) 14.1% U235
Reactor Vessel Height (m) 4.8
Reactor Vessel Diameter (m) 2.0
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KLT-40S Nuclear Steam Suply System
• Reactor Vessel
• Steam Generators
• Main Circulation
Pumps
• Pressurizers
• The Reactor Core
(next Slide)
KLT-40S, 2013 (http://www.iaea.org)
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KLT-40s Core
• The Reactor Core • 121 hexahedral
shrouded FAs
• FAs: 69, 72, or 75 fuel rods, burnable poison rods, and movable control rods
• U-235 enrichment: 14.1%
• Single loading with replacement of all FAs when refueling
Fuel Assembly KLT-40S, 2013 (http://www.iaea.org)
IAEA
KLT-40S Safety Features
• Use passive and
active EFS
• Reactor
Emergency
Shutdown
• Emergency heat
removal
• Emergency Core
Cooling
• Containment
systems
KLT-40S, 2013 (http://www.iaea.org)
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KLT-40S Safety Features
• Emergency Shutdown
• Shutdown control rods
• liquid absorber injection
KLT-40S Reactor Plant for the floating CNPP FPU, presented at IAEA by
Yury P. Fadeev
IAEA
KLT-40S Safety Features
• Emergency Decay
Heat Removal
• Passive design
• Two trains provide
24 hours of cooling
without water
makeup
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KLT-40S Safety Features
• Emergency Core
Cooling
• Safety Injection (5)
• Accumulators (4)
• Recirculation (6)
KLT-40S Reactor Plant for the floating CNPP FPU, presented at IAEA by Yury P.
Fadeev
IAEA
KLT-40S Safety Features
• Emergency
Containment
Pressure
Reduction
System
• Two passive
trains
• Operate 24 hrs
without water
makeup
IAEA
Design, Licensing and Deployment
• The environmental impact assessment for KLT-40S reactor systems was approved by the Russian
• Federation Ministry of Natural Resources in 2002. In 2003, the first floating plant using the
• KLT-40S reactor system received the nuclear site and construction licenses from Rostechnadzor
• (Russia’s nuclear regulator).
• The keel of the first FPU carrying the KLT-40S, the Akademik Lomonosov in the Chukotka
• Region, was laid in 2007. The Akademik Lomonosov is to be completed by the end of 2016 and
• Expected electricity production is by 2017.
IAEA
SMR – iPWR type: integration of NSSS
Integration of
components CAREM NuScale
ACP
100 SMART mPower WEC IRIS IMR
Pressurizer O O out O O O O O
Steam
Generators O O O O O out O O
Pumps NC NC O NC
CRDMs O O O O
SIZE MWth
MWe
100
25
160
45
310
100
330
100
530
180
800
225
1000
335
1000
350
76
IAEA
Identified Potential Technical Issues of SMRs
• Control room staffing for multi-module SMR Plants
• Human factor engineering, implication of digital I&C
• Defining source term for multi-module SMR Plants in
regards to determining emergency planning zone, etc.
• Standardization of first-of-a-kind engineering structure,
systems and components
• Rational start-up procedure for natural circulation SMR
designs
• Power fluctuation and instability in different operating modes
• Conduct of Operation and Operating Limit & Condition
(OLC) for SMRs intended for continuous Load-Follow
operation in off-grid
• Associated safety, regulatory and component reliability
Page 77 of 37
IAEA 4-5 March 2015 78
Newest HTGR designs information (Please contact Mr. Frederik Reistma, Lead of HTGR at [email protected])
9th GIF-IAEA Interface Meeting
Advances in Small Modular Reactor Technology Developments
Updated booklet (September 2014)
IAEA
CEFR SVBR 100 4S PRISM
Full name China Experimental
Fast Reactor
Lead-Bismuth Eutectic
Fast Reactor 100
Super-Safe, Small
& Simple
Power Reactor
Innovative Small Mod.
Designer China Nuclear Energy
Industry Corporation
AKME Engineering
RUSSIAN Federation
TOSHIBA, CRIEPI
JAPAN
GE Hitachi
USA
Reactor type Liquid metal cooled
fast reactor
Liquid metal cooled
fast reactor
Liquid metal-cooled
fast reactor
Liquid metal cooled
fast breeder reactor
Thermal power 65 MW 280 MW 30 MW 840 MW
Electrical power 20 MW 101 MW 10 MW 311 MW
Coolant Sodium Lead-Bismuth Sodium Sodium
S. Pressure Low pressure 6.7 MPa Non pressurized Low pressure
S. Temperature 530oC 500oC 510oC 485oC
Key features Fast neutrons for
irradiation testing;
Indirect Rankine
Cycle, Passive safety
Indirect Rankine cycle Uses heterogeneous
metal alloy core
Design status Detailed Detail Detail Detail
Deployment Connected to
grid 2011
~ 2019 ~ 2022 ?
Liquid-Metal Cooled, Fast Spectrum SMRs (Please contact Mr. Stefano Monti, Head of NPTDS at [email protected])
IAEA
SMRs in terms of Safety Performance
• Further improve passive
safety technology
• Incorporates lessons-learned
from major accidents to
enhance performance of
engineered safety features: • Separation of reactor trip logic and
ESF initiator, diversity in core
cooling and high pressure
depressurization means; station
blackout mitigation systems;
filtered venting
• Resilience and robustness to
multiple external events
80
Page 80 of 37
IAEA 81
Risk-Informed approach and EPZ reduction
• Risk-Informed approach to “No (or reduced) Emergency Planning Zone”
• Elimination or substantial reduction (NPP fences) of the Emergency
Planning Zone
• New procedure developed: Deterministic + Probabilistic needed to
evaluate EPZ (function of radiation dose limit and NPP safety level)
• Procedure developed within a IAEA CRP; discussed with NRC
US Emergency Planning Zone: 10
miles
CAORSO site
France Evacuation Zone:
5 km
IRIS: 1 km
IAEA
Part III
Elements and Approaches to Facilitate SMR
Deployment (The Need of Technology
Roadmap)
IAEA
Elements to Facilitate SMR Deployment
1
2
3
4
5
SMRs with lower generatingcost
Multi-modules SMRdeployment
Passive safety systems
Modification to regulatory,licensing
Transportable SMRs withsealed-fueled
Build-Own-Operate projectscheme
SMRs with enhanced prolifresistance
SMRs with automatedoperation feature
SMRs with flexibility forcogeneration
SMRs inexpensive to buildand operate
Design Development and Deployment Issues Average Ranking
Average Ranking (1 IsMost Important)
IAEA
Elements to Facilitate SMR Deployment
0.5
0.75
1
1.25
1.5
SMRs with lower generatingcost
Multi-modules SMRdeployment
Passive safety systems
Modification to regulatory,licensing
Transportable SMRs withsealed-fueled
Build-Own-Operate projectscheme
SMRs with enhanced prolifresistance
SMRs with automatedoperation feature
SMRs with flexibility forcogeneration
SMRs inexpensive to buildand operate
Design Development and Deployment Issues Agreement Ranking
Standard Deviation(Smaller Value Shows…
IAEA
Approaches to Facilitate Deployment (1)
• Design Development and Deployment Issues
• address key SMR technology innovation (testing and licensing, e.g. multi-
module I&C & control room, modular SG, passive safety systems)
• early collaboration among technology developer, safety authorities and
embarking countries
• Performance indicators for constructability, operability and
maintainability
• address supply chain preparation and qualification, especially to implement
modular engineering/construction
• "time-to-market" is the main risk
• Market Demand for SMRs, Economic Competitiveness, and Non-
Electric Applications
• set of suitable economic indicators should be identified (beyond LCOE) to
evaluate SMR competitiveness: price of FOAK vs n-th of a kind
• SMRs should be competitive (not only in LCOE) with other energy sources
as well as with LRs, otherwise they could lose momentum and interest
IAEA
Approaches to Facilitate Deployment (2)
• Design Development and Deployment Issues
• As a result of Fukushima, reactor designs being retooled with new safety features.
Reactor concepts moving closer to deployment, but early actions needed with
regulatory authorities to define areas of uniqueness of SMR designs
• Question remains, who want SMRs and when potential customers be ready for them.
Consideration needed on future global conditions; e.g., constraints on carbon due to
concerns of climate change, future energy prices due to subsidies for low carbon
technologies, and the continued role that fossil energy will play in the energy mix such
as a transition from coal to natural gas and in some cases to oil shale.
• Performance indicators for constructability, operability and maintainability
• SMRs could be operated and sited in more flexible ways. Power manoeuvring and
non-electricity applications are recognized as additional deployment opportunities.
There is interest by SMR vendors in reducing the site footprint so that SMRs could be
more economical and more flexibly sited.
• SMRs have potential to be competitive with competing energy sources", including
fossil energy (coal and gas) and renewables. Economies from modular production are
needed, and sufficient orders will need to be booked to allow factory production.
Emphasis needs to be placed on considering the factory producibility issues while the
SMRs are still in design.
IAEA
Approaches to Facilitate Deployment (3)
• Performance indicators for constructability, operability and maintainability
• "A critical trade-off between technical/safety features vs. cost/time to market". MS will
need to better understand these issues in making a decision about SMR deployment.
• Market Demand for SMRs, Economic Competitiveness, and Non-Electric
Applications
• IAEA Member States can benefit from having tools to help them assess the viability of
using SMRs." The conditions needed to support deployment of SMRs are very similar
to large NPPs. However discrimination is needed to define where SMRs are unique to
large plants (e.g., smaller EPZ, siting near heat users and populations) and where
they must also fully consider infrastructure and life-cycle requirements (e.g., fuel cycle
back-end).
• "Conditions supporting SMR deployment largely boil down to finance, political and
strategic decisions." These decisions could supported through:
1) Understanding available Contracting Options (BOO, BOT, BOOT)
2) Financial risk Assessment and mitigation
3) Education - becoming an intelligent customer to be able to understand the
differences between SMR technologies.
IAEA
Key Barriers/Challenges to Deployment
• Limited near-term commercial availability of SMR designs
for embarking countries • Capacity building in embarking countries’ nuclear regulatory authority for
advanced reactors depends on the preparedness of vendor countries’
regulatory and licensing infrastructures
• Technology developers to enhance the ability to secure
significant additional EPC contracts from investors to
provide the financial support for design development and
deployment: first domestic, then international markets • Lower price of natural gas in some countries including the US limits the
need of utilities to adopt nuclear power.
• Unless the development and deployment were fully state-funded
• Economic competitiveness over alternatives
• Regulatory, licensing and safety issues in Post Fukushima.
Page 88 of 37
IAEA
Summary
IAEA is engaged in SMR Deployment Issues
11 countries developing ~50 SMR designs with different
time scales of deployment and 4 units are under
construction (CAREM25, HTR-PM, KLT-40s)
Commercial availability, deterministic cost structure,
and operating experience in vendors’ countries is key to
embarking country adoption
Countries understand the potential benefits of SMRs,
but support needed to assess the specific technology
and customize to their own circumstances
Indicators of future international deployment show
positive potential
89
IAEA
THANK YOU VERY MUCH
New Publication on SMR that covers Up-to-
Date Water-Cooled and High Temperature
Gas-Cooled SMR Designs Information
Please download from:
http://www.iaea.org/NuclearPower/SMR
For inquiries on SMR, contact:
Dr. M. Hadid Subki <[email protected]>
IAEA
Programmatic Terminology
• PROGRAMMATIC: Project 1.1.5.2/1000153 (2005 – 2020) • Common Technologies and Issues for Small and Medium-sized Nuclear
Reactors addressed by GC resolution every other year
• Small reactors: <300 MW(e), Medium reactors: 300 700 MW(e)
• Umbrella-Programme that covers the whole spectrum of technologies
• IMPLEMENTATION: IAEA focuses on the current trend of
development & deployment in the Member States:
• Small Modular Reactors: modern, power < 300 MW(e), shop-fabricated
as modules, shippable to sites by roads or rails
• Integral-PWR SMRs deployed as multiple-modules plant
• Marine-based small modular reactors: barge-mounted floating power unit,
transportable NPP, underwater power units
• Mostly water-cooled, but there are some gas-cooled and liquid-metal
cooled fast small reactor designs
91
IAEA
IAEA Activities
SMR Technology Development and Deployment
• One-House approach including Nuclear Energy, Nuclear
Safety, Nuclear Applications, Safeguards and TC to serve
Member States in addressing “Common Technologies and
Issues for SMRs”
• Key activities:
Development of SMR Technology Deployment Roadmap (e.g.
engineering, safety, licensing, regulatory, deployment indicators)
Defining Performance Indicators (e.g. Operability, Safety,
Maintainability, Manufacturability)
Development of Toolkit for Assisting MS in performing Technology
Identification and Assessment
Coordinated Research Projects on post Fukushima R&Ds
Education & Training for Embarking Countries
92
IAEA
Conducted IAEA Activities on SMR in 2014 – 2015 (Publications)
No. Activities Notes
1
Considerations to Enhance the Performance of
Engineered Safety Features in Water-Cooled SMR in
coping with Extreme Natural Hazards
An IAEA Technical Document (TECDOC)
• Contribution to IAEA Action
Plan on Nuclear Safety, #12:
Utilizing Effective R&D
• CM to Finalize the TECDOC
was done: 2 -5 March 2015
2 Technology Roadmap for Small Modular Reactor
Deployments (Nuclear Energy series report)
• US-PUI funded activity.
• Lead by a US-CFE in NPTDS
• CM to Finalize the NE Series:
Polimi, Milano, 14-16 April
3 Environmental Impact Assessment for SMR Deployments
(NE series report) - COMPLETED
• US-PUI funded activity.
• US NRC & CNSC the chairs
• 14 Member States contributing
4 Instrumentation and Control Systems for Small Modular
Reactors (NE series report)
• ORNL & CNSC the chairs
• 9 Member States contributing
• CM to Finalize the NE Series:
Done in 16-20 March
5
Options to Enhance Energy Supply Security using Hybrid
Energy Systems based on SMR – Synergizing nuclear and
renewables (NE series report) - COMPLETED
• EC-JRC & NE/PESS the chairs
• 9 Member States contributing
6 Engineering Designs and Operations of Integral-PWR type
Small Modular Reactors (IAEA-TECDOC)
• Not started yet
• DPP approved in 2014 93
IAEA
Conducted IAEA Activities on SMR in 2014 – 2015 (Technical Meetings)
No. Technical Meetings (TM) Place, Dates
1 TM on Economic Analyses for High Temperature Gas-
Cooled Reactors and Small Modular Reactors
• IAEA, Vienna, Austria
• 24 – 28 August 2015
2 TM on Technology Roadmap for Small Modular Reactor
Development for Near Term Deployment
• IAEA, Vienna, Austria
• 12 – 15 October 2015
3
TM on Technology Assessment of integral-PWR type
Small Modular Reactors for Near Term Deployment in
Embarking Countries
• CNNC, Beijing, China
• Postponed to
5 – 8 September 2016
94