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Introduction to AP1000 major equipment
Introduction to AP1000 major equipment
First generation nuclear power plant: From the 50s to the early 1960s the Soviet Union, the United States and other construction of the first single capacity of about 300MWe nuclear power plants, such as the United States and the British port of Hipigong 1 nuclear power plant, France's Chouz (Chooz) nuclear power plant, Germany Obrigheim (Obrigheim) nuclear power plant, Japan's Meibang 1 nuclear power plant. The first generation of nuclear power plants belong to the prototype reactor nuclear power plant, the main purpose is to test the demonstration form to verify the feasibility of its nuclear power in the implementation of the project. Second generation nuclear power plant: The second generation of nuclear power plants is mainly to achieve commercialization, standardization, serialization, batch, to improve the economy. From the late 1960s to the 1970s, a large number of standardized and serialized nuclear power plants with a single stand-alone capacity of 600-1400MWe were built. Model 212 (600MWe, two-ring pressurized water reactor, represented by American Westinghouse) , A 12-foot fuel assembly), a Model 312 (1000MWe, 3-loop pressurized water reactor, a core with 157 cartridge assemblies, a 12-foot fuel assembly), Model 314 (1040MWe, 3-ring pressurized water reactor, The Model 412 (1200MWe, 4-ring pressurized water reactor, the core has a 193-box assembly, uses a 12-foot fuel assembly), a Model 414 (1300MWe, 4-ring pressurized water reactor, The reactor has a 193 cartridge assembly with a 14-foot fuel assembly), the System80 (1050MWe, 2 loop pressurized water reactor) and a large number of boiling water reactors (BWR) can be included in the second generation nuclear power plant category. France's CPY, P4, P4 '' also belong to Model 312, Model 414 a class of standard nuclear power plant. Japan, South Korea has also built a number of Model 412, BWR, System80 and other standard nuclear power plants. The second generation of nuclear power plants is currently running the world's 439 nuclear power plants (September 2007 statistics) main unit, with a total installed capacity of 372 million kilowatts. Also a total of 34 nuclear power units under construction, with a total installed capacity of 278 million kilowatts. After the triennial nuclear power plant and the Chernobyl nuclear power plant after the accident, countries on the operation of the nuclear power plant in varying degrees of improvement in the safety and economy have improved to varying degrees.
2021-12
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AP1000 master equipment design and manufacturing technology transfer situation
AP1000 master equipment design and manufacturing technology transfer situation
Westinghouse has transferred the nuclear island process and system design, provided technical specifications and guidance maps for major equipment, and the master steam engine design of the main equipment of the system, which was partially transferred by Westinghouse. Other equipment, according to SNPTC and WEC agreed, by the Westinghouse (subcontractor) wing to provide equipment design and manufacturing technology.
2021-12
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The development of AP1000
The development of AP1000
In 1985, Westinghouse commenced the development and research of passive advanced pressurized water reactors AP600, and carried out a large number of experimental studies on the passive safety system. The original design and safety analysis procedures of Westinghouse were modified and developed, and the company developed procedures suitable for the design and safety analysis of passive advanced PWRs. After 13 years of efforts, on September 3, 1998, NRC issued the final design approval of the AP600. The project took 1,300 people/year, 12,000 design documents, and nearly $ 600 million. On the basis of the passive advanced PWR AP600, in December 1999, Westinghouse launched the research and development of the AP1000, which lasted for 5 years.
2021-12
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AP1000 Safety Review
AP1000 Safety Review
1. On March 28, 2002, Westinghouse submitted to the US Nuclear Regulatory Commission the application for the “standard design certificate” for AP1000 standard design. The application includes AP1000 design control documents, probabilistic safety analysis report, etc. 2. On July 25, 2002, the US Nuclear Regulatory Commission accepted the application, and according to 10 CFR Part 52 of the federal regulations and other relevant laws and regulations concerning how to deal with serious accidents, and on the basis of independently carrying out a review and part of the tests, the "pre-certification review" for the AP1000 design was completed, to confirm that the AP600-related tests and analysis program can be used for AP1000 design. 3. The US Nuclear Regulatory Commission put forward a total of more than 700 questions regarding the AP1000 design review, and completed the "final safety evaluation report" for the AP1000 design through independent review and verification. In September 2004, the "final safety evaluation report" was officially released. 4. On September 23, 2004, Westinghouse received NRC's Final Design Approval for AP1000. 5. After the hearing conducted according to the relevant laws of the United States, on December 30, 2005 NRC issued the “standard design certificate” for AP1000 standard design to Westinghouse.
2021-12
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