Technology Development, Design and Safety Features of the CNP300 and A New Small PWR

Transcription

1 Technology Development, Design and Safety Features of the CNP300 and A New Small PWR and A New Small PWR By LIN Qian Shanghai Nuclear Engineering Research and Design Institute (SNERDI)

2 Content SNERDI and Nuclear Power Technology R&D The CNP300 Technology Concept of a new small modular reactor -2-

3 About SNERDI Shanghai Nuclear Engineering Research and Design Institute (SNERDI), located in Shanghai, east China, was established in Currently more than 1200 staffs, more than 900 engineers in SNERDI. SNERDI has become a subsidiary of the State Nuclear Power Technology Corporation (SNPTC) since June

4 About SNPTC Position of SNPTC On behalf of Chinese government, to introduce advanced 3 rd generation nuclear technology with Westinghouse. To develop China s own brand name nuclear power technology through assimilation, absorption and innovation; SNPTC is a key entity and platform for 3 rd generation nuclear power technology introduction, project construction and self-reliance development. Business Scope of SNPTC Nuclear Power technology Research & Development, Application, Technology Support & Consulting Service; Power & Grid s Project Engineering, Procurement, Construction and Technology Service. -4-

5 About SNPTC 10 Subsidiaries of SNPTC No. Units Fields of development 1 SNERDI Development of NI design techniques 2 SNPTRD Basis of nuclear technologies R&D 3 SNPDRI 4 SNZ 5 SNPSC Development of CI design techniques, grid planning and design techniques Development of manufacture techniques of nuclear-used Zirconium materials Development of the key operation supporting techniques of NI equipment 6 SNPEMC Development for manufacture techniques of NI key equipment 7 SNPAS Digital I&C development 8 SDEPCI R&D of biomass energy technologies and large-scaled thermal power technology 9 SNPEC Development of engineering information management system (IMS) 10 SPERI Development of Power Equipment -5-

6 SNERDI Organization President Vice President Assistant President Chief Engineer Deputy Chief Engineer R & D and Expert Committee President Office & International Affairs Department of Planning & Business Department of Reactor Core Design R & D Centers Department of Human Resources Department of Quality Management Department of Component Research & Design Affiliated Company Department of Finance Department of Project Management Department of Nuclear Process Systems Department of Resources Management Department of General Technology Department of Electric Instrumentation & Control Office of Internal Audit Department of R & D Management Department of Civil Engineering & Common Services Department of NPP Tech Support Department of Consulting -6-

7 Main Achievement Design of the 1 NPP in mainland China, Qinshan 300MWe NPP (1991). Design of Pakistan Chashma NPP Unit 1 (2000). Design of Chashma Units 2, which connected to grid in the end of Technical support to Chinese imported CANDU-6 6 HWR. Development and design of Chinese CNP

8 Major Activities Ongoing Design for Chashma NPP-3/4. Design of Hongyanhe CPR1000. NPP, AP1000 Self-Reliance project for Sanmen and Haiyang NPP. SNERDI is the overall design institute and responsible for overall, and BOP design. Hongyanhe Design Contract Signing Ceremony Design of follow up AP1000 inland and coastally. Contract Signing Ceremony for Overall Design of AP1000 San Men -8-

9 Major Activities Ongoing China s s Large Advanced PWR R&D Project The purpose for Large Advanced PWR Project is to develop and construct large advanced passive PWR based on the transferred AP1000 Technology. LPP-1: CAP1400 concept design has passed state review and in the phase of preliminary design. Testing loop construction for 6 items, including PCCS, container cooling and IVR etc has been fully started. CAP1400 Demonstration Project LPP-2: CAP1700 concept design has finished Better Economy, Equivalent or higher safety -9-

10 Technical Capability CAP1700 Enhanced PWR CNP1000 CANDU 6 CPR1000 CAP1400 AP1000 Advanced Passive PWR CNP300 SMR -10-

11 Content SNERDI and Reactor R&D The CNP300 Technology Concept of a new small modular reactor -11-

12 First CNP300 Reactor: Qinshan NPP A 2-loop, 2 300MWe PWR plant designed by SNERDI (overall, NI) and ECEPDI(CI). Power to grid in Dec. 15, 1991, 12 th cycle under operation. The First Self-design and Selfconstruct NPP in Mainland China -12-

13 Follow-up CNP300 Reactors: Chashma NPP A turn-key project. A 2-loop, 2 325MWe PWR plant. Many improvements were made based on QNPP: Foundation, EFWS, layout, etc. C-1 1 1st power to grid in June 2000, well operated by PAEC. C-2 2 (340 MWe) ) has been turned over to PAEC in 2011 C-3/C-4 4 is under design and construction The First NPP Exported -13-

14 Main Parameters Thermal Power: 966(998.6)MWt(ESF ESF:1035MWt) Fuel type: ,fuel enrichment <5% FA No:121 Fuel cycle:15 months RCS pressure: 15.2MPa Coolant average temperature: 302 RV Diameter: 3.7m,height: 10.7m Vertical U tube natural circulation SG Steam pressure 5.54MPa -14-

15 Continuous Improvement During the Follow-up Engineering Design and Construction Early design principle for QNPP (China First NPP): Safety first Conservation and more redundant safety margin Based on the feedback of long time operation, improvement of equipment & IC, newly methodology and tools,the design is optimized to increase the economy. Power output: 300MWe upgrade to 340MWe Designed life:30 years extended to 40 Fuel improvements Digital protect system Conventional system and electric generation system improvement Safety ESF system improvement PSA Severe accident -15-

16 FA300 Fuel Assembly FA300-1:( ), Zr-4 cladding,25gwd/tu FA300-2 fuel assembly:( ) Opt. Zr-4 cladding,30gwd/tu FA300-3 fuel assembly:( ) Debris filter,30gwd/tu FA300-4 fuel assembly:(2006- ) Large grain size pellet, Zr-Nb cladding,40gwd/tu -16-

17 ESF Philosophy Auxiliary feedwater system Emergency core cooling system High pressure safety injection system (4) Accumulator and boron injection system (4) Low pressure safety injection system (2) Containment system Containment spray system (2) Containment isolation system Containment hydrogen recombiner system C-2 core damage frequency for internal initiating events at power is calculated to be 7.4E-6 events per reactor year -17-

18 Performance improvement Possible Further Improvement Linear power density upgraded from 136 to 170 w/cm Fuel cycle: 15 to 18 months Design life: 40 to 50 years Safety improvement Passive safety features ECCS with passive equipment (CMT) Feedback from Fukushima accident -18-

19 Operating Performance of QNPP-I Excellent operation records achieved in recent years. 2007: 8 of the 13 WANO index is above the average, in which 5 index is in the advanced level. 2008: 8 of the 13 WANO index is above the average, in which 6 index is in the advanced level. 2009: 8 of the 13 WANO index is above the average, in which 6 index is in the advanced level. Periodical Safety Review (PSR) (14 items) Safety analysis Equipment Qualification Ageing management Year Load factor Capability factor

20 CNP300 Proved and reliable technology Meet the current regulation and utilities demand Based on Qinshan, Chashma NPPs good operation performance Continues improvement and optimizing Advanced reactor characteristics Enhanced safety and economy -20-

21 Content SNERDI and Reactor R&D The CNP300 Technology Concept of a new small modular reactor -21-

22 SNERDI Research Activities on SMR SNERDI research work on SMR was initiated in the end of Early activities focused on the investigation of kinds of existing SMRs concept worldwide. In 2010, a research project was set up at SNERDI to develop a new kind of small PWR. The preliminary conceptual design is carried out: Core design, NSSS T/H, RV, SG, ESF Now, preliminary concept was established -22-

23 Main Goals Goals Based on the design philosophy of existing advanced reactor concept worldwide, to innovatively bring out a new G-III + PWR. More safety than current deployed G-III reactors. Reasonable and competitive economy with current reactors. Good engineering feasibility by implementing proved technology, no extreme challenges for main components. Extend the reactor series to meet different utilities' requirements. -23-

24 A Multipurpose SMR Small grid Process heat District heating SMR Power offshore platform Desalinization Driving cargo ships -24-

25 Design Principle Refer to the EUR & URD, stand on the toe of utilities. Good engineering flexibility, multipurpose. Employing proved technology and components to improve the reliability and economy. Standardized and modularized NSSS, RCS modules are fully manufactured in factory and transported to site for installation. Defense in depth. Diversified safety systems include active and passive features. The ultimate heat sink of passive long term cooling is air. Enhance safety features of spent fuel storage. Environment and public friendly, eliminate the requirements for offsite emergency. PSA is applied to achieve the safety goals and get a design balance. -25-

26 Main Parameters Thermal power: 450MWt Design life: More than 60 years Refueling cycle: About 3 years Availability factor: More than 95% No operator intervention: More than 7 days -26-

27 RCS Integrated RCS Integrated RCS: SG, PZR, RCP, CRDM are all merged into RV. No large pipes to eliminate LB-LOCA. Minimizing primary coolant penetrations to reduce the SB- LOCA. Simplified RCS to enhance the natural circulation. Large reactor coolant inventory in RV to increase the thermal inertia. -27-

28 Fuel & Core Design Make use of the proved fuel assembly of CNP300, developed by SNERDI. Based on the QNPP & Chashma NPP operation data, Proved & Reliable. Suitable for lower burnup feature of SMR. Shorten development cycle and reduce R&D cost. Core design 69 FA 3 years fuel cycle, 2/3 refueling No boron in coolant FA300-4: Large grain size pellet, Zr-Nb cladding, 40GWd/tU -28-

29 Steam Generator Internal steam generator 8 SGs located annularly, one failure SG will hardly affect the reactor operation. With the primary coolant outside, tubes are in compression, which enhances the reliability of the SGs, and reduces the SGTR frequency. Tubes in service inspection and failure tubes blocking are available by secondary side. SGs are also served as part of secondary side decay heat removal devices. OTSG Superheated steam is generated,no need for steamwater separation. Possible option: Saturated steam SG, Steam-water is separated outside the RV, using steam drum to enhance the second loop stability. -29-

30 RCP Main Components 8 RCPs located on the RV. The parameters and technical requirements for RCP are within the current technology. Small non-seal pumps based on proven technology are adopted, which can be easily manufactured. CRDM CRDM is based on proven technology applied in the QNPP and Chashma NPP. Only small improvement is needed. RCP & CRDM are not internal components submerged in primary coolant. No tough challenge. -30-

31 Containment Double containments: steel & concrete. Steel containment is submerged in a water pool, which is the ultimate heat sink. In-containment spent fuel pool, to ensure the safety of spent fuel under SBO. All radioactivity is contained in the containment during normal operation. -31-

32 Safety Concept: Active AND Passive ESF philosophy Based on active and passive technique, redundant and diverse. Based on the inherent characteristics of integrated Small PWR. No LB-LOCA Higher Natural Circulation Performance Larger Coolant Inventory Less Decay Heat Lower Power Density Active and passive system Passive decay heat removal by SG secondary side Active decay heat removal system Gravity driving low pressure water injection system Passive steel containment cooling by external pool Severe accident -32-

33 Current Work Current R&D General concept optimizing RCS and main components concept verification ESF concept verification Phenomena identification Accident analysis Early PSA Economy analysis The concept design and the fundamental demonstration are expected to finish by 2014, followed by the verification tests. -33-

34 Test Program Integrated scaling T/H experiment RCS T/H test Passive decay heat removal by SG secondary side Passive injection system test Passive containment cooling Components test Hydraulic test for the integrated RV SG performance test Internal pressurizer test CRDM test Others -34-

35 SMR Flexible, multiple purpose Integrated system Proved fuel Proved RCP and CRDM Diversified safety system Simplified auxiliary and BOP system Intrinsic Safety, Competitive economy -35-

36 Thank you for your attention! Reactors (SMRs) for Near Term Deployment, Vienna, 5 9 December