Domestic fourth-generation nuclear power technology has been research and development to avoid similar Fukushima accident

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The accident at the Fukushima nuclear power plant caused by the Great Earthquake in Japan caused the world’s attention to the safety of nuclear power to reach an unprecedented height, and it also triggered domestic thinking on the development of nuclear power. Experts introduced today that China's high-temperature gas-cooled reactors have the safety features of the fourth-generation nuclear energy system, which can avoid similar accidents.

The accident occurred at the Fukushima nuclear power plant mainly using the second-generation nuclear power system, and China's major science and technology project “Large Advanced PWR and High-Temperature Gas-Cooled Reactor Nuclear Power Plant” was the main research direction—large-scale advanced PWR nuclear power plant and high temperature Air-cooled reactor nuclear power plants belong to the category of third-generation nuclear power systems and fourth-generation nuclear power systems, respectively.

There are usually three ways for modern nuclear power technology to deal with emergency emergencies in nuclear power plants. One is to further increase the way and reliability of power supply, that is, the second generation of improved type; the second is to put water on high ground and use gravity to let the water flow to the reactor. The core, that is, the three-generation "passive" technology; the third is to simply change the physical characteristics of the reactor core, greatly reduce the energy emitted by the unit space core, and ultimately make the reactor no need cooling water or other coolant, they can emit heat to their own So that nuclear fuel is not damaged.

Zhang Zuoyi, dean and chief engineer of the Institute of Nuclear Energy and New Energy Technology at Tsinghua University, told reporters that the third type of high-temperature gas-cooled reactor is used in China. Its power density is 1/30 of that of pressurized water reactors. The core volume of a pressurized water reactor producing 1 million kilowatts of nuclear fission energy is about 30 cubic meters, and the core volume of a high-temperature gas-cooled reactor is 900 cubic meters. Moreover, it divides a large million-kilowatt reactor into 10 small 100,000-kilowatt modules to increase the surface heat dissipation area. This ensures that the reactor will automatically dissipate heat without coolant cooling and that the fuel elements will not be damaged. Because of this safety feature, high-temperature gas-cooled reactors are internationally known as Melt-Free reactors, meeting the safety standards of the fourth-generation nuclear energy system. This characteristic has been verified by a large number of scientific experiments in actual reactors.

At the beginning of March 2011, the State Council approved the project of Shandong Rongcheng Shidao Bay High Temperature Gas-cooled Reactor Nuclear Power Plant. The construction of the first high-temperature gas-cooled reactor commercial demonstration power station in China was formally initiated. This is the first high-temperature air-cooling in China with independent intellectual property rights. The reactor demonstration power station is one of the most significant developments in the major special projects of the “Large Advanced PWR and High-Temperature Gas-Cooled Reactor Nuclear Power Plant” in the past two years.

In fact, as early as 2009, news of the construction of the first tank of concrete in the demonstration project of the high-temperature reactor nuclear power plant continued to be heard, but no action was yet to be taken. Zhang Zuoyi said that the safety review of nuclear power plants is very strict. In the past two years or so, the National Nuclear Safety Administration has organized hundreds of people to review issues in various aspects, and now it has been determined that all of them meet the safety requirements and the equipment has Processing in Shanghai. “At present, we have built an environment that simulates the high-temperature and high-pressure helium of the nuclear power plant reactor at No. 200 Tsinghua University to test the equipment to be installed.”

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