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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;
-34-
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