QIN Guopeng, ZHANG Liying, LI Jinkui, et al.Study on the Load-bearing Performance for the Upper Shell Welds of Nuclear Fuel[J].Electric Welding Machine, 2024, 54(7): 110-115.
QIN Guopeng, ZHANG Liying, LI Jinkui, et al.Study on the Load-bearing Performance for the Upper Shell Welds of Nuclear Fuel[J].Electric Welding Machine, 2024, 54(7): 110-115. DOI: 10.7512/j.issn.1001-2303.2024.07.16.
Study on the Load-bearing Performance for the Upper Shell Welds of Nuclear Fuel
Stainless Steel Electron Beam Welding is often considered the optimal upgrade for manual GTAW welding. However
in some welding structures with shear strength requirements
the narrow characteristics of electron beam welds may affect their load-bearing performance. Since the welds of nuclear fuel cylinder components need to withstand long-term high temperature and pressure
radiation creep stress
and chemical corrosion in the reactor core
the shear load-bearing performance of electron beam welds has been questioned by experts. To ensure the reliability of the core product welding structure
the geometric dimensions and load-bearing area of electron beam (EB) welds and manual GTAW welds were first compared and analyzed
and it was found that the width of EB welds is only 53.5% of GTAW welds
and the load-bearing area is only 48.8% of GTAW welds. Then
through theoretical calculation and working condition analysis
it was concluded that the maximum load-bearing capacity of the cylinder component weld is 134
765 N
and the theoretical load-bearing capacity of both EB and GTAW welds is much greater than this value. Finally
through physical testing
it was found that the load-bearing performance of EB and GTAW welds is equivalent and both are greater than the load-bearing capacity of the cylinder component itself. It was ultimately proven that the EB welds can meet the design requirements for product load-bearing performance under normal and accident conditions
providing support for the smooth advancement of research on the localization of nuclear fuel.
LI F L,CHENG S H,SHAO Z J,et al. Influence of process parameters on ferrite content in GTAW cladding metal of 304L stainless steel[J]. Welding & Joining,2020(3):24-28.
SHAO X J,XIE H,XIONG F R,et al. Study on Environmental Fatigue Correction Factor of PWR Material Coolant Environment[J]. Atomic Energy Science and Technology,2020,54(6):1085-1091.
林诚格. 非能动安全先进压水堆核电技术[M]. 北京:原子能出版社,2010.
Sargeni A,Fouet F,Ivanov E,et al. Uncertainties propagation in the UAM numerical rod ejection benchmark[J]. Annals of Nuclear Energy,2020,141:107339.
OCT 95 503-84,核反应堆活性区焊接总技术要求、验收规则和检验方法[S]. 俄罗斯核行业标准,1984.
谢小飞.事故工况深燃耗燃料元件材料特性研究[D].黑龙江:哈尔滨工程大学,2012.
XIE X F. Research of Material Properties of High Burnup Fuel Element Under Accident Conditions[D]. Heilongjiang:Harbin Engineering University,2012.