CAP1400 Design &Construction

Transcription

1 CAP1400 Design &Construction Lin Tian

2 Content Nuclear Power Development Strategy in China after Fukushima Accident CAP1400 R&D, Engineering design& construction AP1000 Self-reliance Supporting Projects 2013/6/28-2-

3 Nuclear Power Development Strategy after Fukushima Accident

4 Energy Supplying & consuming structure Fossil Fuel (69%) US electricity generation Residential (35%) Renewable (9%) Nuclear (21%) (Total: Million GWh, 2008) Commercial (35%) Industrial (25%) Other (1%) Other (5%) Fossil Fuel (83%) Renewable (15%) Nuclear (2%) China electricity generation (Total: 3.643/5.0 Million GWh, 2009/quarter,2013) Industrial (75%/71%) Residential (12.5/14) Commercial (10/12) Other (2.5%)

5 USA FRANCE NPPs all over the world 1 4 JAPAN 50 3 CHINA RUSSIA KOREA 23 4 INDIA 20 7 Under operation 13620MWe Under construction 31660MWe CANADA 19 GERMANY 9 Units under construction:china28/ all the world 65 CZECHIC 6 5

6 NPPs in mainland China Jingyu Beijing Xudabao Donggan Hongyanhe Baiyin Luoyang Shidaowan Haiyang Tianwan 17 units in operation 28units under construction Other 24 units under permission More than 80 units proposed Peng an Fengdu Fuling Fangchenggang Changde Xianning Jiyang Pengze Taohuajiang Xuyu Wuhu Shanghai Fangjiashan Sanming Fuqing Putian Zhangzhou Lufeng Daya Bay Ling ao I,II Taishan (EPR) Yangjiang Changjiang Sanmen Wenzhou Ningde Qinshan I,II,III -6-

7 NPP Development Strategy of China On Oct.24,2012, Chinese government issued a Mid to long term nuclear power development plan( ), determined national overall planning. 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

8 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.

9 Large Advanced PWR Project R&D and Engineering

10 Project launched Background CAP1400 Large advanced PWR Project 2007 National Science and Technology Major Project 2013/6/28-10-

11 Background Why SNERDI? SNERDI is one of the three research and design institutes of NPP in China. 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. -11-

12 Background Why SNERDI? The 1 st NPP in mainland of China, Qinshan 300MWe NPP with 2 loops PWR. Connected to grid in Dec. 15, 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

13 Background Re-innovation AP1000 Standardization : Localization Design + feedbacks + Safety enhanced after Fukushima CAP1000 CAP150 CAP1400 Integrated SMR FCD in April 2014 Passive GIII PWR Technology imported from WEC The first selection for next first batch NPP CAP1700 Conceptual design study finished Other CAPs

14 Introduction CAP1400 three main inputs 1 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 2 Based on the accumulated experience and achievements of the world's first batch of AP1000 units 3 Based on lessons from Japanese Fukushima nuclear accident 2013/6/28-14-

15 Introduction CAP1400 general picture 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 stateof-the-art technology, a guarantee of development vision.

16 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

17 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

18 General plant data Nuclear steam supply system Steam flow rate at nominal conditions kg/s (BEF) Steam pressure 6.16MPa(a) Steam temperature o C (BEF) Feedwater temperature o C Reactor coolant system Reactor operating pressure 15.5MPa(a) Core coolant inlet temperature o C Core coolant outlet temperature o C Mean temperature rise across core 39.4 o C

19 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/m 3 General plant data Fuel material Sintered UO 2 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

20 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 o C Base material SA508,Grade3,Class1 Total height, inside 12635mm Steam generator Type U type, Vertical Number 2 Total tube outside surface area m 2 Number of heat exchange tubes Tube outside diameter 17.48mm Tube material Inconel 690-TT

21 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 21642m 3 /h

22 General plant data Pressurizer Total volume 70.79m 3 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 o C Design leakage rate 0.1volume %/day

23 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 o C(TDF without plugged tube)

24 General plant data Generator Type Direct Driven Rated power MVA 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

25 Main technical features Items Primary system Safety system Severe accident mitigation Seismic condition Regulation compliance Specifications 2-loop configuration, 1 hot and 2 cold pipes per loop Passive system, no need of operator action in 72 hrs IVR(Internal-Vessel Retention) and hydrogen igniters 0.3 g SSE(Safe Shutdown Earthquake), and 0.5g HCLPF 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

26 Innovations Nuclear plant design is scaled up and reactor power is boosted by 20%; 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 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 Steam Generator is self-designed. By applying dryer with proprietary IPR, steam quality is improved Self-designed structural shield building with steel plate concrete (SC) is capable of resisting malicious crash of large commercial aircraft 2013/6/28-26-

27 Innovations The reactor protection system based on FPGA (Field Programmable Gate Array) technology provides higher level of safety Independently developed COSINE software system is used to conduct design validation and safety evaluation Half-speed large turbine generator that is developed and manufactured independently in China is employed. Designed with innovation and optimization for steel containment vessel, safety allowance increased, system layout improved and accessibility optimized 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 2013/6/28-27-

28 Innovations According to latest standard, radioactive waste treatment system is designed innovatively to minimize the amount of waste exhausted to environment during normal operation 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 2013/6/28-28-

29 Lessons learned from Fukushima nuclear accident 1 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 2 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 3 Based on the requirement of current codes, the dry site requirement for CAP1400 can be satisfied which prevents all safety-grade SSC from flooding 2013/6/28-29-

30 Lessons learned from Fukushima nuclear accident 4 Without being dependent on alternating current, the passive safety system is able to keep the CAP1400 safe within 72 hours after accident initiation 5 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 6 Moreover, the cooling capability for spent fuel pool is also enhanced 2013/6/28-30-

31 Validation test Modified PXS FIV RC&Internals PCCS VT Hydraulic test for RC IVR SG 2013/6/28-31-

32 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

33 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..

34 Research & Design 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-

35 Demonstration Project Rongcheng in Shandong as the site for demonstration plant 1 SNPTC will complete the R&D of CAP1400 in The first unit will be approved and certified in 2013 including safety reviews by NNSA 2013/6/28-35-

36 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-

37 Demonstration Project Milestones of CAP1400 demonstration plant: 2014 FCD 2018 Connected to Grid 2011 Basic Design Completed 2010 Conceptual Design Completed

38 Demonstration Project

39 AP1000 self-reliance supporting project

40 AP1000 Self-reliance Supporting Project Locations 山东海阳项目 Haiyang AP1000 Project Shandong Province 浙江三门项目 Sanmen AP1000 Project Zhejiang Province

41 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 , and is expected to power generation in December 2014.

42 AP1000 Self-reliance Supporting Project Canned motor pump tested and qualified pump went through interns, engineering and duration tests 42

43 AP1000 Self-reliance Supporting Project Equipment manufacturing and installation RPV PZR SG RCS Piping Core internals Polar crane CVTH 43

44 AP1000 Self-reliance Supporting Project Role of SNERDI 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

45 Approach to NPP Factors considered Demand Government support Public acceptance Industry capability First NPP Financing Legislative Frame Personnel 2013/6/28-45-

46 Approach to NPP NPP provider Export? Invest? Transfer? Technology Financing Fuel&Waste O&M experiecne Sustainability Reliability Spent fuel and radioactive waste 2013/6/28-46-

47 Approach to NPP How to obtain the first NPP? New comer Provider Approaches Turn key Build-Own-Operate Build-Operate-Transfer 4 Technology transfer 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. 2013/6/28-47-

48 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

49 Challenge Faced by Developing Countries The environmental, security and social problems become risks undertaken by all relevant parties in the case of shortage of substantial support from: 1 national capability and industry for supporting nuclear units 2 human and technical resource for maintaining the as-qualified status of units as per current licensing basis 3 politically stable society, and government as well, for security assurance 4 adequate financial support for sustainable operating nuclear units The big challenge for developing countries comes out to be who is going to take the liability of potentially environmental crisis?

50 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.

51 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 Build a reasonable mechanism for risk allocation with legally binding, e.g. stake-holding, joint venture etc 2 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

52 Q&A Thanks 2013/6/28-52-