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CAP1400 Design &Construction

Lin Tian

2013-06-27

2013/6/28 -2-

Content

Nuclear Power Development Strategy in China after Fukushima Accident

CAP1400 R&D, Engineering design& construction

AP1000 Self-reliance Supporting Projects

Nuclear Power Development Strategy after

Fukushima Accident

Fossil Fuel (69%)

Renewable (9%)

Nuclear (21%)

Residential (35%)

Other (1%) Other (5%)

Industrial (25%)

Commercial (35%)

US electricity generation

(Total: 3.831 Million GWh,

2008)

Fossil Fuel (83%)

Renewable (15%) Residential (12.5/14)

Nuclear (2%) Other (2.5%)

Industrial (75%/71%)

Commercial (10/12)

China electricity generation

(Total: 3.643/5.0 Million GWh,

2009/quarter,2013)

Energy Supplying & consuming structure

USA

FRANCE

JAPAN

RUSSIA

KOREA

INDIA

CANADA

CHINA

GERMANY

CZECHIC

104

58

50

33

23

20

19

17

9

6

1

4

3

10

4

7

28

Under operation 13620MWe

Under construction 31660MWe

NPPs all over the world

5

Units under construction:China28/ all the world 65

Tianwan

★Beijing

Qinshan I,II,III

Daya Bay Ling’ao I,II

Shanghai

Taohuajiang

Xianning

Pengze

Shidaowan

Other 24 units under permission

17 units in operation

Fangjiashan

Changjiang

Ningde

Fuqing

Yangjiang

Taishan (EPR)

Sanmen

Haiyang

Hongyanhe

Fangchenggang

28units under construction

Jingyu

Luoyang

Peng’an

Fuling

Changde

Baiyin

Xudabao Donggan

Xuyu

Wenzhou

Zhangzhou Putian

Lufeng

Wuhu

Jiyang

Sanming

Fengdu

More than 80 units proposed -6-

NPPs in mainland China

On Oct.24,2012, Chinese government issued a “Mid to long term nuclear power

development plan(2011-2020)”, determined national overall planning.

NPP Development Strategy of China

Safely and Effectively Develop Nuclear Power

Adopting the strictest Safety Standards and the most Advanced Technology

AP1000 and its localized re-innovation technology for future

To build to be a Nuclear Power Giant

Strategic Opportunities Period of NPP

More rooms in nuclear power development in China if all GIII

units are successfully operated.

Energy demand

Environment pressure

Advanced technology GIII and GIII +

Investment and enough manufacturing capability .

Large Advanced PWR Project R&D and

Engineering

2013/6/28 -10-

Background

Project launched

CAP1400

Large advanced PWR

Project 2007

National Science

and Technology

Major Project

SNERDI is one of the three research and design institutes of NPP in China.

-11-

1. Class A qualification of engineering design

2. Class A qualification of engineering consulting

3. Class A qualification of project supervising

4. Class A qualification of radioactive protection evaluation

5. Class A qualification of environment impact evaluation

6. Qualification of nuclear pressure retaining component design (issued by

NNSA)

7. Class1, Class2, and Class 3 qualification of pressurized vessel design

8. Class A qualification of architectural decoration design.

9. In total, 16 Class A, 5 Class B certificates and/or qualifications.

Background

Why SNERDI?

The 1st NPP in mainland of China, Qinshan

300MWe NPP with 2 loops PWR. Connected

to grid in Dec. 15, 1991.

Design of Pakistan Chashma NPP Unit 1.

Technical support to CANDU-6 HWR

imported from Canada.

Design of Chashma Units 2-4, Units 2 has

been connected to grid at the end of 2010

Development and design of Chinese

CNP1000 with 1000MWe.

Design of Hongyanhe CPR1000 NPP

Why SNERDI?

Background

AP1000 CAP1000

Passive GIII

PWR Technology

imported from

WEC

Standardization :

Localization Design

+ feedbacks

+ Safety enhanced

after Fukushima

The first

selection for

next first batch

NPP

CAP1400

CAP150

CAP1700

Integrated

SMR

FCD in April

2014

Conceptual

design study

finished

Other CAPs

Background

Re-innovation

2013/6/28 -14-

Introduction

• Based on the experience of the PWR technology R & D for more than 40 years, construction and safe operation of 16 NPPs for

more than 20 years in China 1

• Based on the accumulated experience and achievements of the world's first batch of AP1000 units 2

• Based on lessons from Japanese Fukushima nuclear accident 3

CAP1400 three main inputs

Introduction

A two-loop advanced passive pressurized water reactor nuclear power

technology , with a generating capacity about 1500 MWe for a single

Unit , R&D by SNPTC,.

Based on the introduced U.S. Westinghouse AP1000 technology, through

upgrading plant capacity, optimizing overall parameters, balancing plant

design and innovating major equipment design, CAP1400 further

enhances nuclear safety and plant economic competiveness, improves

environmental compatibility and optimizes the convenience for

operation & maintenance.

The CAP1400 is an option for harmonious environment, a model of state-

of-the-art technology, a guarantee of development vision.

CAP1400 general picture

General plant data

General plant data

Reactor thermal output 4058MWth

Power plant output 1500MWe

Power plant efficiency, net 34.4%

Mode of operation Baseload and load follow

Plant design life 60 years

Plant availability target> 93%

Seismic design, SSE 0.3g

Primary coolant material Light water

Secondary coolant material Light water

Moderator material Light water

Thermodynamic cycle Rankine

Type of cycle Indirect

General plant data

Safety goals

Core damage frequency<

1E-6/Reactor-Year

Large early release frequency<

1E-7/Reactor-Year

Occupational radiation exposure<

1.0Person-Sv/RY

Operation action time

72Hours

General plant data

Nuclear steam supply system

Steam flow rate at nominal conditions 2246.8kg/s (BEF)

Steam pressure 6.16MPa(a)

Steam temperature 274.8 oC (BEF)

Feedwater temperature 226.7oC

Reactor coolant system

Reactor operating pressure 15.5MPa(a)

Core coolant inlet temperature 284.3 oC

Core coolant outlet temperature 323.7 oC

Mean temperature rise across core 39.4 oC

General plant data Reactor core

Active core height 4267mm

Equivalent core diameter 3370mm

Average linear heat rate 18.1kW/m

Peak linear heat rate 47.06kW/m

Average core power density 109.7Mw/m3

Fuel material Sintered UO2

Fuel element type Fuel rod

Cladding material ZIRLO™

Outer diameter of fuel rods 9.5mm

Rod array of a fuel assembly Square 17x17

Number of fuel assemblies 193

Enrichment of reload fuel at equilibrium core 4.95 Weight%

Fuel cycle length 18 Months

Average discharge burnup of fuel 53102MWd/tU (assembly averaged)

Control rod absorber material Ag-In-Cd(Black), Ag-In-Cd /304SS(Gray)

Soluble neutron absorber H3BO3

General plant data

Reactor pressure vessel

Inner diameter of cylindrical shell 4430mm

Wall thickness of cylindrical shell 22.5mm

Design pressure 17.3MPa(a)

Design temperature 350 oC

Base material SA508,Grade3,Class1

Total height, inside 12635mm

Steam generator

Type U type, Vertical

Number 2

Total tube outside surface area 14666.5m2

Number of heat exchange tubes 12606

Tube outside diameter 17.48mm

Tube material Inconel 690-TT

General plant data

Reactor coolant pump

Pump type Canned pump or hermetically sealed, wet

winding motor pump(backup)

Number of pumps 4

Pump speed 1500rpm

Head at rated conditions 111m

Flow at rated conditions 21642m3/h

General plant data

Pressurizer

Total volume 70.79m3

Steam volume: full power 37.08m3

Heat power of heater rods 1950kW

Primary containment

Overall form(spherical/cylindrical) Cylindrical

Dimensions- diameter 43m

Dimensions- height 73.6m

Design pressure 0.443Mpa

Design temperature 150 oC

Design leakage rate 0.1volume %/day

General plant data

Residual heat removal systems

Active/passive system Passive

Safety injection system

Active/passive system Passive

Turbine

Number of turbine sections per

unit(e.g.HP/MP/LP)

1HP/3LP

Turbine speed 1500rpm

HP turbine inlet pressure 5.78Mpa（TDF without plugged tube）

HP turbine inlet temperature 273.2oC（TDF without plugged tube）

General plant data

Generator

Type Direct Driven

Rated power 1722.2MVA

Active power 1550MW

Voltage 27kV

Frequency 50 Hz

Condenser

Type Multi-pressure (cooling towers) or Single

pressure (direct cooling)

Feedwater pumps

Type Motor driven

number 3

Items Specifications

Primary system 2-loop configuration, 1 hot and 2 cold pipes per loop

Safety system Passive system, no need of operator action in 72 hrs

Severe accident mitigation IVR(Internal-Vessel Retention) and hydrogen igniters

Seismic condition 0.3 g SSE(Safe Shutdown Earthquake), and 0.5g HCLPF

Regulation compliance Compatible worldwide including US, Europe &CHINA

Main Technical Features of CAP1400 includes:

Passive Safety Concept with Highest Nuclear Safety Criteria

Proven technology with Simplified System & Equipment

Modularization Construction with Reduced Construction Duration

Upgraded Nuclear Safety Features Based on Lessons Learned from

Fukushima Accident

Reliable Operation Expectancy, excellent economic performance

Main technical features

2013/6/28 -26-

Innovations

1

• Nuclear plant design is scaled up and reactor power is boosted by 20%;

2

• Reactor is designed with innovation. Reactor core employs 193 boxes of high-performance fuel assemblies, with lower linear power density and MOX fuel (mix of uranium and plutonium) loading capacity

3

• Reactor coolant pump with 50Hz is employed to avoid frequency converter from long-time running, which improves operation reliability of RCP and reduces energy consumption

4

• Steam Generator is self-designed. By applying dryer with proprietary IPR, steam quality is improved

5

• Self-designed structural shield building with steel plate concrete (SC) is capable of resisting malicious crash of large commercial aircraft

2013/6/28 -27-

Innovations

6

• The reactor protection system based on FPGA (Field Programmable Gate Array)

technology provides higher level of safety

7 • Independently developed COSINE software system is used to conduct design

validation and safety evaluation

8 • Half-speed large turbine generator that is developed and manufactured

independently in China is employed.

9

• Designed with innovation and optimization for steel containment vessel, safety allowance increased, system layout improved and accessibility optimized

10

• Further enhancing nuclear station’s fortification against earth quake, flood and other extreme natural disasters. Especially, passive safety systems are capable of self-sufficiency by supplying water to them after 72 hours of accident initiation to make sure the NPP is safe

2013/6/28 -28-

Innovations

11

• According to latest standard, radioactive waste treatment system is designed innovatively to minimize the amount of waste exhausted to environment during normal operation

12

• Improve accident management procedures, enhanced post-accident monitoring to improve the capacity for power plant emergency response

13

• Absorb the feedback from AP1000 self-reliance supporting project, (Sanmen,Haiyang) • Including :the latest design change, licensing application feedback, construction permit requirements,

modularization

2013/6/28 -29-

• Further enhancing nuclear station’s fortification against earth quake, flood and other extreme natural disasters. Especially, passive safety systems are capable of self-sufficiency by supplying water to them after 72 hours of accident initiation to make sure the NPP is safe

1

• Safe shutdown earthquake for CAP1400 is 0.3g peak ground acceleration which covers most plant sites. Furthermore, the seismic evaluation demonstrates that the HCLPF of all safety-grade SSCs are ≥0.5g

2

• Based on the requirement of current codes, the dry site requirement for CAP1400 can be satisfied which prevents all safety-grade SSC from flooding 3

Lessons learned from Fukushima nuclear accident

2013/6/28 -30-

• Without being dependent on alternating current, the passive safety system is able to keep the CAP1400 safe within 72 hours after accident initiation 4

• From 72hours to 7days, the non-safety grade measures are available to offer reactor core cooling; 7 days after accident initiation, the reactor core can still be cooled with some extra off-site assistance

5

• Moreover, the cooling capability for spent fuel pool is also enhanced 6

Lessons learned from Fukushima nuclear accident

2013/6/28 -31-

Validation test

VT

PXS

PCCS

IVR

SG

Hydraulic

test for

RC

FIV

RC&Internals

Modified

Validation Test

ACME integrated bench PCS water distribution test bench PCS integrated test building

IVR metal layer heat transfer test bench IVR-ERVC test bench

Hot performance test bench for SG

steam separators

Research & Design

China’s domestic participants

Chinese Government has paid

high attention to the

development of CAP1400 by

listing it as National Science

and Technology Major

Projects.

Over 100 organizations

including Chinese nuclear

power companies, equipment

fabrication enterprises,

research institutes and

universities have participated

in CAP1400 technology

development..

International Cooperation

CAP1400 gains support and cooperation from dozens of foreign corporate

including those from the US, Germany and Japan;

• Westinghouse(US) provides design consultation;

• L&M (US) participates in instrumental control system

development;

• OSU (US) participates in test verification;

• EMD(US) and KSB (Germany) participate in the development of

Reactor Coolant Pump;

• GRS (Germany) participates in engineering design verification;

• Laboratories of OECD provide large amounts of test data;

• Corporates from US, Canada and Japan participate in equipment

material research and test verification;

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Research & Design

2013/6/28 -35-

Rongcheng in Shandong as the site for demonstration plant

• SNPTC will complete the R&D of CAP1400 in 2013 1

• The first unit will be approved and certified in 2013 including safety reviews by NNSA 2

Demonstration Project

Demonstration Project

Demonstration project with two CAP1400 units is going to be constructed in

Shidao Bay Rongcheng Shandong province in China

The construction duration for the first unit is expected to be no more than 56

months from the start of structural concrete placement to grid connection and

is expected to be in commercial operation in Dec 2017

As scheduled, 18 months later, the FCD for second unit will be initiated with

construction duration being decreased to be 48 months.

The standardized design of CAP 1400 has been adjusted to take the site

characteristics into consideration.

-36-

2010

Conceptual Design Completed

2011

Basic Design Completed

2014

FCD

2018

Connected to Grid

Milestones of CAP1400 demonstration plant:

Demonstration Project

Demonstration Project

AP1000 self-reliance supporting project

Locations

浙江三门项目

Sanmen AP1000 Project

Zhejiang Province

山东海阳项目

Haiyang AP1000 Project

Shandong Province

AP1000 Self-reliance Supporting Project

Construction and realization Sanmen and Haiyang ：

• Opening items of engineering design and equipment manufacture closed

• No subversive technology and engineering risks exist.

FCD in March 2009，and is expected to

power generation in October 2014，CVTH .

FCD in September 2009，CVTH installation

on Mach 29 2013, and is expected to power

generation in December 2014.

2013 . 3 . 1 2013 . 3 . 1

AP1000 Self-reliance Supporting Project

42

pump went through interns, engineering and duration tests

Canned motor pump tested and qualified

AP1000 Self-reliance Supporting Project

CVTH

2013.1.29

RPV PZR

SG RCS Piping

Core internals Polar crane

43

Equipment manufacturing and installation

AP1000 Self-reliance Supporting Project

Owner:

• Overall Design of AP1000 Self-

Reliance project for Sanmen and

Haiyang

• Licensing application

WEC and Shaw:

• Subcontract of Westinghouse/CBI

Industries

AP1000 technology transferring (TT),

Digestion and Absorption

AP1000 Self-reliance Supporting Project

Role of SNERDI

2013/6/28 -45-

Approach to NPP

First NPP

Public

acceptance

Financing

Personnel

Industry

capability

Governm-

ent support

Legislative

Frame

Demand

Factors considered

2013/6/28 -46-

NPP provider

• Reliability • Sustainability

• Spent fuel and

radioactive

waste

• Invest? • Export?

• Transfer?

Technology Financing

O&M

experiecne Fuel&Waste

Approach to NPP

2013/6/28 -47-

How to obtain the first NPP?

Approach to NPP

New comer Provider

Approaches

• Turn key 1

• Build-Own-Operate 2

• Build-Operate-Transfer 3

• Technology transfer 4

The prevailing business models and their variations actually

define the ultimate ownership of a facility, and also show the

ways in which the risks are allocated.

Challenge Faced by Developing Countries

Nuclear power is actually a capital intensive project or

investment with concerns on demonstration of:

the least cost alternative for electricity generation capacity

expansion

the cost efficient decision-making offering benefits like green

house gas (GHG) emission reduction, energy security and

diversity, and fuel cost volatility, while solving thereby

introduced environmental, security and other social problems

The environmental, security and social problems become risks undertaken by all

relevant parties in the case of shortage of substantial support from:

The big challenge for developing countries comes out to be

who is going to take the liability of potentially environmental

crisis?

Challenge Faced by Developing Countries

• national capability and industry for supporting nuclear units 1

• human and technical resource for maintaining the as-qualified status of units as per

“current licensing basis 2

• politically stable society, and government as well, for security assurance 3

4 adequate financial support for sustainable operating nuclear units

Exploring Future Advancing

Nobody (e.g. an entity) else but the government could make the

best availability of the national resources for mitigating

potential consequences of the environmental crisis.

Thus, currently prevailing business models, say the PPPS, BOT,

and BOO, actually do little help for relevant entities to survive

or deal with the stated challenge without government support.

Exploring Future Advancing

For sure a demonstrably environment benign, profitable (eventually) and cost

efficient project of building a nuclear power in a developing country, a new

framework of business may be explored with the following focuses:

1 • New NPP in a politically stable country will be preferred

2

• Build a reasonable mechanism for risk allocation with legally binding, e.g. stake-holding, joint venture etc

• within the binding system, licensing relevant technology or IPR to partners, building training and qualifying

system, advancing technical localization, and providing services along with the life cycle of the unit

3

• Recognizing the GHG mitigation potential of nuclear power, thus

increasing its attractiveness to investors and lenders

2013/6/28 -52-

Thanks

Q&A