【摘 要】
:
The CAP1400,large-scale advanced PWR demonstration project,will be built by our country,after the innovation work on the imported technology of AP1000.During it
【机 构】
:
Department of Reactor Engineering Research and Design,
【出 处】
:
Annual Report of China Institute of Atomic Energy
论文部分内容阅读
The CAP1400,large-scale advanced PWR demonstration project,will be built by our country,after the innovation work on the imported technology of AP1000.During its design,whether the fatigue life curve of domestic main pipe material can be revised by the RG1.207 guidelines is a design problem,and also is an urgent problem of localized key equipment in Chinese third-generation nuclear power technology.
The CAP1400, large-scale advanced PWR demonstration project, will be built by our country, after the innovation work on the imported technology of AP1000. Drawing its design, whether the fatigue life curve of domestic main pipe material can be revised by the RG1. 207 guidelines is a design problem, and also is an urgent problem of localized key equipment in Chinese third-generation nuclear power technology.
其他文献
With the finishing of China Advanced Research Reactor project construction and B,C commissioning phase various irradiation experiments and application program h
This paper research on the effect of various load(including 190,200,230,250,270,300,350,380 MPa)on the creep performance at 625℃,and analysis the fracture surf
The high-level radioactive glass will be put in the deep underground repository as one of the final disposal methods.During the long-term process of geological
As the core components of the reactor,the performance of fuel element is one of the main influence factors for nuclear safety and economy.Using annular fuel ele
The temperature of the T-Ti target rise comparatively fast when the beam on the target iscomparatively large,and then the tritium of the target escape from the
A508-3 steel used in the reactor pressure vessel(RPV)belongs to low alloy ferrite steel which has obviously embrittlement in low temperature.And the irradiation
The objectives of the approved project—New domestic zircaloy fuel assembly irradiation is to conduct irradiation at research reactor for experimental fuel asse
To obey the related regulation and standard of our country,calculating and analyzing the criticality safety problem of UF_6 transportation packing of UX-30 type
As for the hexagonal spent fuel assembly’s dry storage container of Tianwan VVER reactor,a critical safety analysis study of high-density storage is carried ou
A new-type passive decay heat exchanger has been put forward for the requirements of largetype size fast reactor,which can make little flux passing through the