Advances in Development and Deployment of Small Modular ... · Modular Advanced Reactor (SMART)...

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:



~ 1985:



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:


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


• 28 – 31 October 2013

3 TC Interregional Workshop on Design, Technology and

Deployment Considerations for SMRs


• 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

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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

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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

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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

IAEA

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

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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)

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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

IAEA

Argentina: CAREM-25

• Full name: Central Argentina de Elementos

Modulares

• Designer: National Atomic Energy

Commission of Argentina (CNEA)




• Thermal/Electrical Capacity: 100.0 MW(t) /

31 MW(e) Gross

• Pressure/Temp: 12.25 MPa / 326oC


• 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 Inlet Temperature (°C) 284


Fuel Assembly (hexagonal ) 108 of 127 position for fuel rods


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)


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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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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• Containment

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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

IAEA

United States of America: NuScale

• Full name: NuScale

• Designer: NuScale Power Inc., USA

• Reactor type: Integral Pressurized Water

Reactor




165 MW(t)/45 MW(e)

• Modules per plant: (1 – 12) modules


• 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%


SG Steam (MPa) 3.1

Refueling Intervals 24 months

Fuel Assembly 17x17 PWR Enriched UO2 Fuel with

Zircaloy Cladding


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

IAEA


• 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

IAEA


• 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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• 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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• 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




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

IAEA

mPower – 1

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mPower – 2

IAEA

• 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

IAEA

HTR-PM: Basic Plant Parameters

Reactor Thermal Capacity (MW) 2 x 250


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

IAEA

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

IAEA

China: ACP100

• Full name: Advanced China PWR 100

• Designer: Nuclear Power Institute of China,

China National Nuclear Corporation (CNNC)


• Coolant/Moderator: light water


• Thermal/Electrical Capacity: 385MW(t) /

120 MW(e)


• 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

IAEA

Russian Federation: KLT-40S

• Designer: OKBM Afrikantov – Russian

Federation

• Reactor type: PWR – Floating Nuclear

Cogeneration Plant

• Coolant/Moderator: H20


• 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

IAEA

KLT40S- Basic Plant Parameters Thermal Capacity (MW) 150


Expected Capacity Factor (%) 70

Thermal efficiency (%) 23.3



Core Inlet Temperature (°C) 280

Stem pressure (MPa) 3.82

Steam temperature (°C) 290


Fuel Assembly Canned, hexahedral


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)

IAEA

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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• 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


• Emergency Decay

Heat Removal

• Passive design

• Two trains provide

24 hours of cooling

without water

makeup

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• 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


• Emergency

Containment

Pressure

Reduction

System

• Two passive

trains

• Operate 24 hrs

without water

makeup

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• 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

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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

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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

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


• 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


• 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.

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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

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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


• 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


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


• 24 – 28 August 2015

2 TM on Technology Roadmap for Small Modular Reactor

Development for Near Term Deployment


• 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

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