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600MW Xiapu Sodium Cold Fast Reactor Demonstration Power Station Project-Core Thermal Calculation Verification Project Passed Acceptance
On April 23, 2023, North China Electric Power University (hereinafter referred to as "Huadian") and Tianjin High-end Equipment Research Institute of Tsinghua University organized experts to conduct technical review and project acceptance on the project "Three-dimensional Thermal Fluid Transient Calculation Verification of Demonstration Fast Reactor Vessel and Reactor Internal Components" undertaken by the Institute of Advanced Energy Equipment Technology of Tsinghua University.
Project Report Expert Discussion
The project team made a detailed report on the calculation model, model simplification, calculation conditions and calculation results, and the expert group listened to the report and conducted serious consultation and discussion. The final review by the expert group, unanimously agreed to pass the project acceptance.
Three-dimensional model calculation model of sodium-cooled fast reactor
Sodium-cooled fast reactor is the fourth generation nuclear reactor, the reactor thermal hydraulic behavior is complex, because the medium is sodium, thermal experiments to verify a certain degree of difficulty, so sodium-cooled reactor in-reactor thermal simulation is important and difficult. The core thermal calculation project jointly undertaken by Huadian and our institute is the input condition for structural design, which determines the success or failure of reactor structural design. Internationally, both France and Japan have profound lessons from the failure of exploration. After years of hard work, Huadian and our institute (who can be identified) have fully communicated with the owner and the design unit China Institute of Atomic Energy (can you specify the name of the unit), repeated calculations and verifications, and successfully completed the project through unremitting efforts., Has made its own contribution to the implementation of national key projects.
Partial cloud map display
The Xiapu 600MW Demonstration Fast Reactor (CFR600) project uses the CFR600 pool sodium-cooled fast neutron reactor independently developed by China National Nuclear Corporation. It is China's first fast reactor nuclear power demonstration project. The demonstration fast reactor project is a major nuclear energy science and technology project approved by the state, and it is an important part of China's nuclear energy "three steps", fast reactor "three steps" and science and technology power "three steps" development strategy, which is of great significance.
Report of Advanced Energy Equipment Technology Research Institute Text/Chen Junwei Figure/Shao Rong
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