AP1000介绍（英文原版）.doc

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1、AP1000The AP1000 is an advanced 1000 MWe nuclear power plant that uses the forces of nature and simplicity of design to enhance plant safety and operations and reduce construction costs.The Westinghouse AP1000 is a logical extension of its AP600 plant. Design studies have shown that a two-loop confi

2、guration could produce over 1000 MWe with minimal changes in the AP600 design. The primary purpose of developing the AP1000 was to retain the AP600 design objectives, design details and licensing basis, while optimizing the power output, thereby reducing the resulting electric generation costs.PASSI

3、VITY AND SAFETYAs in AP600, the AP1000 design uses passive safety systems to enhance the safety of the plant and to satisfy the Nuclear Regulatory Commissions (NRC) safety criteria. These systems use only natural forces, such as gravity, natural circulation, and compressed gas. No pumps, fans, diese

4、ls, chillers, or other rotating machinery are used in the passive safety sub-systems. The passive safety systems include passive safety injection, passive residual heat removal, and passive containment cooling. All these passive systems have been designed to meet the NRC single-failure criteria and

5、its recent criteria, including TMI (Three Mile Island) lessons-learned and unresolved/generic safety issues. Probabilistic Risk Assessment (PRA) tools have also been used to quantify the safety of the design.SIMPLICITY The passive safety systems are significantly simpler than the traditional PWR saf

6、ety systems. They do not require the large network of safety support systems needed in typical nuclear plants, such as AC power, HVAC (heating, ventilation & air conditioning), cooling water systems and seismic buildings to house these components. Simplification of plant systems, combined with incre

7、ased plant operating margins, reduces the actions required by the operator. The AP1000 has 50 percent fewer valves, 83 percent less piping, 87 percent less control cable, 35 percent fewer pumps and 50 percent less seismic building volume than a similarly sized conventional plant. These reductions in

8、 equipment and bulk quantities lead to major savings in plant costs and construction schedules.NUCLEAR STEAM SUPPLY SYSTEM (NSSS) & FUELThe AP1000 NSSS plant configuration consists of two Delta-125 steam generators, each connected to the reactor pressure vessel by a single hot leg and two cold legs.

9、 There are four reactor coolant pumps that provide circulation of the reactor coolant for heat removal. A pressurizer is connected to one of the cold leg piping to maintain subcooling in the Reactor Coolant System (RCS). The two-loop, 1090 MWe plant retains the same basic design of the AP600. Change

10、s to the design to increase the electricity output have been minimized to allow the direct application of most of the existing design engineering already completed for the AP600. Examples of design features that remain unchanged include the nuclear island footprint and the core diameter. Major compo

11、nent changes incorporated into the AP1000 design include a taller reactor vessel, larger steam generators (Delta-125), a larger pressurizer and slightly taller, canned reactor coolant pumps with higher reactor coolant flows. The designs for these reactor components are based on components that are u

12、sed in operating PWRs or have been developed and tested for new PWRs. Performance of the passive safety features have been selectively increased, however, these changes have been accomplished with small changes to the AP600 plant design. The AP1000 fuel design is based on the 17x17 XL (14 foot) desi

13、gn used successfully at plants in the U.S. and Europe. As with AP600, studies have shown that AP1000 can operate with a full core loading of MOX fuel. CONSTRUCTION Like the AP600, the AP1000 utilizes modularization technique for construction, which allows many construction activities to proceed in p

14、arallel. This technique reduces the plant construction calendar time, which saves the IDC (Interest During Construction) cost and reduces the risks associated with plant financing. The AP1000 has a site construction schedule of 36 months from first concrete to fuel loading.LICENSING Westinghouse has

15、 submitted documentation to the United States Nuclear Regulatory Commission (US NRC) thereby initiating the process of obtaining a Final Design Approval (FDA) of the AP1000 from the US NRC. As the AP1000 shares much in common with the AP600, both in technical design philosophy and technical design d

16、etail, it is anticipated that the NRC review and approval process will be significantly faster than the six years needed to review and approve the AP600. TESTINGAll necessary testing have been performed in the development of AP600. AP600BackgroundThe AP600 is an advanced 600 MWe nuclear power plant

17、that uses the forces of nature and simplicity of design to enhance plant safety and operations and reduce construction costs.Westinghouse is in the process of obtaining design certification for the AP1000 a more powerful plant based on the AP600.The AP600 - A Cooperative EffortAs part of the coopera

18、tive U.S. Department of Energy (DOE) Advanced Light Water Reactor (ALWR) Program and the Electric Power Research Institute (EPRI), the Westinghouse AP600 team has developed a simplified, safe, and economic 600-megawatt plant to enter into a new era of nuclear power generation. Designed to satisfy th

19、e standards set by DOE and defined in the ALWR Utility Requirements Document (URD), the Westinghouse AP600 is an elegant combination of innovative safety systems that rely on dependable natural forces and field-proven technologies.Simplified Plant SystemsThe Westinghouse AP600 design simplifies plan

20、t systems and significant operation, inspections, maintenance, and quality assurance requirements by greatly reducing valves, pumps, piping, HVAC ducting, and other complex components. The AP600 safety systems are predominantly passive, depending on the reliable natural forces of gravity, circulatio

21、n, convection, evaporation, and condensation, instead of AC power supplies and motor-driven components.Extensive Use of Field-Proven TechnologyAlthough the AP600 uses simplified and passive plant systems to an unprecedented extent to enhance plant safety and operations, the effectiveness of the tech

22、nology has been demonstrated through years of operations and testing. The AP600s major components are based on years of reliable operating experience. The canned motor reactor coolant pumps have been in use by the US Navy for decades. The steam generators, pressurizer, fuel, and reactor vessel are a

23、ll based on field-proven technology with incremental improvements developed as a result of operating experience. The passive safety systems are an extension of the technology used previously, since Westinghouse-supplied PWRs have had accumulators for injection of core cooling water without the use o

24、f pumps for many years. The AP600 is the result of a logical progression in plant design.Safety and Licensing CertaintyThe AP600 provides a high degree of public safety and licensing certainty. It draws upon over 40 years of experience in light water reactor components and technology, so no demonstr

25、ation plant is required. The AP600 has received final design approval from the US NRC.Comprehensive Test ProgramsDuring the AP600 design program, a comprehensive test program was carried out to verify plant components, passive safety systems components, and containment behavior. When the test progra

26、m was completed at the end of 1994, AP600 became the most thoroughly tested advanced reactor design ever reviewed by the U.S. Nuclear Regulatory Commission (NRC). The test results confirmed the exceptional behavior of the passive systems and have been instrumental in facilitating code validations.Ex

27、tensive Industry ReviewThe Westinghouse AP600 reactor has been designed as part of the Advanced Light Water Reactor (ALWR) Program sponsored by the U.S. DOE and EPRI. Following an extensive review by the U.S. Nuclear Regulatory Commission, the AP600 received final design approval on September 3, 199

28、8. A detailed design program (FOAKE-First-of-a-Kind-Engineering) was completed under the sponsorship of DOE, the Advanced Reactor Corporation (ARC), and EPRI.Passive Safety FeaturesThe Westinghouse AP600 is a 600 MWe reactor which utilizes passive safety features that, once actuated, depend only on

29、natural forces such as gravity and natural circulation to perform all required safety functions. These passive safety systems result in increased plant safety and can also significantly simplify plant systems, equipment, and operation.-Plant FeaturesThe Westinghouse AP600 isnt just an advanced nucle

30、ar power plant- it represents a new way of doing business that addresses the needs of the new utility environment. The AP600 is helping to change the way the world views construction of new nuclear power plants. A Simplified PlantIt is crucial that new nuclear power plants be easier and less expensi

31、ve to build, operate, and maintain. The AP600 requires 50% fewer valves, 80% less safety grade piping, 70% less control cable, 35% fewer pumps (no safety grade pumps), and 45% less seismic building volume than other conventional reactors.A New Kind of SafetyWestinghouse commercial nuclear power plan

32、ts have an excellent safety record. There are more plants safely operating with Westinghouse technology than any other kind. The safety of these operating plants is achieved by substantial amounts of complex, redundant emergency equipment that requires electrical power and occasional operator action

33、s. These are referred to as active safety features. The AP600 achieves safety by relying on the forces of nature, such as gravity, natural circulation, convection, evaporation, and condensation. By relying on these forces, there is no need for complex active systems and operator actions.Economics Dr

34、iven By Simplicity - Not SizeSimplification helps to reduce capital costs and provides a hedge against regulatory driven operating and maintenance costs by eliminating equipment which is subject to regulation. The AP600s capital cost for a twin unit station is expected to be about 15% less than for

35、conventional twin 600 MWe unit stations. Projected operating and maintenance costs are 35% less than the current industry average. Economic performance driven by simplicity rather than scale allows generating companies to add capacity in AP600s smaller increments that more closely match demand growt

36、h.-Passive SafetyAP600 Design ObjectivesThe primary design objective of the AP600 was to provide a greatly simplified plant design that meets NRC regulatory requirements, meets or exceeds NRC safety goals and those of the ALWR Utility Requirements Document, and addresses past safety issues, while be

37、ing economically competitive with other power generation systems over the full operating cycle. This objective is to be met using experience-based components so that plant prototype or demonstration models are not required. Simplification of plant systems, combined with increased plant operating mar

38、gins, reduces the actions required by the operator in the event of an accident. The AP600 design requires no operator actions to maintain a safe configuration following a design basis accident. The design target for the AP600 is to technically support elimination of the emergency planning zone beyon

39、d the site boundary. Simpler systems, combined with the U.S. licensing reforms of 10CFR52, increase the licensing certainty of the AP600 in international markets.Implementation of the passive safety features greatly reduces the operation, maintenance and testing requirements of the AP600. The AP600

40、has been designed to have a shorter construction schedule through the use of modular construction techniques that are similar to those applied in ship construction. The construction design objective is a 36-month schedule from first concrete pour to the fuel load. An added benefit of this approach i

41、s that a significant portion of the quality assurance inspections can be completed in the factory before the modules are delivered to the construction site. Passive Safety Features OverviewThe AP600 uses passive safety systems to enhance the safety of the plant and to satisfy NRC safety criteria. Th

42、ese systems use only natural forces, such as gravity, natural circulation, and compressed gas. No pumps, fans, diesels, chillers, or other rotating machinery are used in the passive safety sub-systems. A few simple valves are used to align the passive safety systems when they are automatically actua

43、ted. In most cases these valves are fail safe (i.e., they require power to stay in their normal, closed position; loss of that power causes them to open to their safety alignment. This power is normally supplied by class lE uninterruptible power supplies). These passive safety systems are significan

44、tly simpler than typical PWR safety systems. In addition to being simpler, the passive safety systems do not require the large network of safety support systems needed in typical nuclear plants, such as AC power, HVAC (heating, ventilating, air conditioning) and cooling water systems and seismic bui

45、ldings to house these components. This simplification includes eliminating the safety-grade emergency diesel generators and their network of support systems, air start, fuel storage tanks and transfer pumps, and the air intake/exhaust system. As a result, support systems no longer need to be safety

46、grade and can be simplified or eliminated. The features of the AP600 passive safety systems include passive safety injection, passive residual heat removal, and passive containment cooling. All these passive systems have been designed to meet the NRC single-failure criteria and its recent criteria,

47、including TMI lessons-learned and unresolved and generic safety issues. PRAs have also been used to quantify the safety of the design. Passive Core Cooling SystemThe AP600 passive core cooling system (PXS) performs two major functions: Safety Injection and Reactor Coolant Makeup for Inventory The AP

48、600 has a passive residual heat removal (PRHR) subsystem that protects the plant against transients that upset the normal steam generator feedwater and steam systems. Westinghouse analysis results, using NRC-approved codes, has shown that the PRHR subsystem satisfies the NRC safety criteria for loss of feedwater, feedwater line breaks, and steam line breaks with a single failure. Anticipated transients without reactor trip have also been analyzed and shown to result in peak RCS pressures of about 2900 psig, well within NRC criteria. The Passive RHR Heat ExchangerThe Pass