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作 者:汪海[1] 孙胜[1] 童明炎[1] 戴钰冰[1] 吴红伟[1] WANG Hai;SUN Sheng;TONG Mingyan;DAI Yubing;WU Hongwei(st Sub-Institute of Nuclear Power Institute of China,Chengdu 610005,China)
出 处:《机械工程师》2021年第11期100-102,108,共4页Mechanical Engineer
摘 要:对M310型核主泵专用屏蔽转运桶进行设计研究,使屏蔽转运桶的屏蔽能力、结构强度满足GB 11806规范的要求。通过采用QAD-CG程序进行屏蔽计算、使用Co-60放射源实测衰减倍数、屏蔽验证计算相结合的方法开展了屏蔽能力设计。通过采用LS-DYNA有限元仿真模拟跌落试验与ANSYS-structural有限元仿真模拟运输加速度冲击试验相结合的方式开展了结构强度设计。在实测最小剂量率衰减倍数为110倍时,表面最大剂量率为0.24 m Sv/h、距表面2 m处最大剂量率为0.46 m Sv/h,小于规范限值。在0.3 m跌落试验仿真分析中,最大应变为1.81%,最大比较应力为554.36 MPa,小于ASME标准限值。在2g运输加速度冲击试验仿真分析中,薄膜应力强度为50.02 MPa、薄膜加弯曲应力强度为50.34 MPa,小于ASME标准限值。屏蔽转运桶的屏蔽能力、结构强度满足GB11806规范的要求。This paper designs&studies M310 type nuclear main pump special shield transport barrel,makes the shielding capacity and structural strength of the barrel meets the requirements of GB11806 standard.The shielding design is carried out using QAD-CG program,Co-60 radioactive source measure attenuation factor and shielding effectiveness verification calculation.The structural strength design is carried out using the combination of LS-DYNA finite element simulation of drop test and ANSYS-structural finite element simulation of transportation acceleration impact test.When the attenuation factor of the measured minimum dose rate is 110,the maximum dose rate is 0.24 mSv/h on the surface and 0.46 mSv/h on the distance of 2 m from the surface.In the simulation analysis of 0.3 m drop test,the maximum strain is 1.81%and the maximum comparative stress is 554.36 MPa,which is less than ASME standard limit value.In the 2g transportation acceleration impact test simulation analysis,the membrane stress intensity is 50.02 MPa,the membrane plus bending stress intensity is 50.34 MPa,both are less than ASME standard limit value.The shielding capacity and structural strength of the shield transport barrel meets the requirements of GB11806 standard.
分 类 号:TL932.1[核科学技术—辐射防护及环境保护]
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