大亚湾核电站反应堆厂房楼层反应谱分析评估
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摘要
大亚湾核电站核岛厂房的抗震分析遵循技术输出国-法国M310型机组的土建技术规范RCC-G, 采用简化的阻抗函数法计算地基岩土的作用。根据大亚湾厂址的地基岩土特点,拟采用更为精确的三维连续半空间边界子结构法来考虑地基岩土的作用,并与原设计进行对比。另外,在原设计中采用多组时程作为地震输入,取各组计算结果的平均值作为设计值的基础(称为“平均”法)。在研究中基于相同的时程,拟分别采用“平均”法和更为常用的“包络”法,处理多组时程的响应。基于上述两方面,通过反应堆厂房的地震响应计算,得到核电站系统设备重要的设计基础数据-楼层反应谱(FRS),并将计算的楼层反应谱同设计谱进行比较,从而对设计方法及其结果进行评估,为电站的抗震设计裕量评估和安全管理提供可资参考的结论。
The seismic analysis of nuclear island of Daya Bay Nuclear Power Plant(NPP) was just in accordance with the approaches in RCC-G standard for the model M310 in France, in which the simplified impedance matrix method was employed for the consideration of soil's function. In this paper the more sophisticated 3D half-space continuum impedance method based on the Green functions is used to analyze the function of soil. In addition, multi-group of input time histories was used in the seismic response analysis in the existing design and their average of responses lor each group was taken as the design basis. The same multi-group of input time histories was used in the seismic re- sponse analysis in this study, but the average and enveloped value of responses for each case are calculated respectively to account for the uncertainty of input motions. Focused on the above two issues, the seismic responses of the reactor building are calculated and the floor response spectra (FRS). a very important data for the design of nuclear system and equipment, are generated and then compared with the corresponding design values, so that the evaluation and discuss on the design method and results are conducted. Some useful conclusions hopefully to provide some important references to the assessment of seismic safety margin for the NPP in operation are taken.
The seismic analysis of nuclear island of Daya Bay Nuclear Power Plant(NPP) was just in accordance with the approaches in RCC-G standard for the model M310 in France, in which the simplified impedance matrix method was employed for the consideration of soil's function. In this paper the more sophisticated 3D half-space continuum impedance method based on the Green functions is used to analyze the function of soil. In addition, multi-group of input time histories was used in the seismic response analysis in the existing design and their average of responses lor each group was taken as the design basis. The same multi-group of input time histories was used in the seismic re- sponse analysis in this study, but the average and enveloped value of responses for each case are calculated respectively to account for the uncertainty of input motions. Focused on the above two issues, the seismic responses of the reactor building are calculated and the floor response spectra (FRS). a very important data for the design of nuclear system and equipment, are generated and then compared with the corresponding design values, so that the evaluation and discuss on the design method and results are conducted. Some useful conclusions hopefully to provide some important references to the assessment of seismic safety margin for the NPP in operation are taken.
引文
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[2] Stevenson J D. US experience in seismic re-evaluation and verification programs[J].Nuclear Engineering and Design, 1998, 182:35-46.
[3] Liambia J M, et al. Sensitivity of Seismic Structural Response to Interpretation of Soils Data[J]. Soil Dynamics and Earthquake Engineering, 1993, 12:337-342.
[4] Robin K, et al. New seismic design spectra for nuclear power plants [J]. Nuclear Engineering and Design, 2001, 203: 249-257.
[5] Bahaa M, et al. Soil-structure interaction in fuel handling building [J]. Nuclear Engineering and Design, 1998, 181: 145-156.
[6] Halbritter A L, et al. Dynamic Analysis of VVER Type Nuclear Power Plants Using Different Procedures for Consideration of Soil-Structure Interaction Effects[J]. Nuclear Engineering and Design, 1998. 182: 73-92.
[7] Pentti Varpasuo. The development of the floor response spectra using large 3D model[J.]. Nuclear Engineering and Design, 1999, 192:229-241.
[8] Nam-Ho Lee, et al. Seismic Capability Evaluation of the Prestressed/reinforced Concrete Containment, Yonggwang Nuclear Power Plant Unit 5 and 6 [J]. Nuclear Engineering and Design, 1999, 192:189-203.
[9] Chen J T, et al. Preliminary Perspectives Gained from Individual Plant Examination of External Events (IPEEE) Seismic and Fire Submittal Review[J], Nuclear Engineering and Design, 1999, 181:91-104.
[10] RCC-G. Adaptation for the Model M310 (1000MWe-PWR) of the RCC-G 900 MWe-PWR-Edition[S]. 1986.
[11] ASCE STANDARD 4-86. Seismic Analysis of Safety-Related Nuclear Structures and Commentary on Standard for Seismic Analysis of Safety-Related Nuclear Structures[S]. New York: ASCE, 1987.
[12] Wong H L, et al. Soil Structure Interaction: A Linear Continuum Mechanics Approach (CLASSI) [Z]. Dept. of Civil Engineering, Univ. of Southern California, CE79-03, 1980(Draft).
[13] NRC Regulatory Guide 1.60-1973. Design Response Spectra for Seismic Design of Nuclear Power Plants[S].
[14] NRC Regulatory Guide 1. 122-1978. Development of Floor Design Response Spectra for Seismic Design of Floor-supported Equipment or Components[S].
[2] Stevenson J D. US experience in seismic re-evaluation and verification programs[J].Nuclear Engineering and Design, 1998, 182:35-46.
[3] Liambia J M, et al. Sensitivity of Seismic Structural Response to Interpretation of Soils Data[J]. Soil Dynamics and Earthquake Engineering, 1993, 12:337-342.
[4] Robin K, et al. New seismic design spectra for nuclear power plants [J]. Nuclear Engineering and Design, 2001, 203: 249-257.
[5] Bahaa M, et al. Soil-structure interaction in fuel handling building [J]. Nuclear Engineering and Design, 1998, 181: 145-156.
[6] Halbritter A L, et al. Dynamic Analysis of VVER Type Nuclear Power Plants Using Different Procedures for Consideration of Soil-Structure Interaction Effects[J]. Nuclear Engineering and Design, 1998. 182: 73-92.
[7] Pentti Varpasuo. The development of the floor response spectra using large 3D model[J.]. Nuclear Engineering and Design, 1999, 192:229-241.
[8] Nam-Ho Lee, et al. Seismic Capability Evaluation of the Prestressed/reinforced Concrete Containment, Yonggwang Nuclear Power Plant Unit 5 and 6 [J]. Nuclear Engineering and Design, 1999, 192:189-203.
[9] Chen J T, et al. Preliminary Perspectives Gained from Individual Plant Examination of External Events (IPEEE) Seismic and Fire Submittal Review[J], Nuclear Engineering and Design, 1999, 181:91-104.
[10] RCC-G. Adaptation for the Model M310 (1000MWe-PWR) of the RCC-G 900 MWe-PWR-Edition[S]. 1986.
[11] ASCE STANDARD 4-86. Seismic Analysis of Safety-Related Nuclear Structures and Commentary on Standard for Seismic Analysis of Safety-Related Nuclear Structures[S]. New York: ASCE, 1987.
[12] Wong H L, et al. Soil Structure Interaction: A Linear Continuum Mechanics Approach (CLASSI) [Z]. Dept. of Civil Engineering, Univ. of Southern California, CE79-03, 1980(Draft).
[13] NRC Regulatory Guide 1.60-1973. Design Response Spectra for Seismic Design of Nuclear Power Plants[S].
[14] NRC Regulatory Guide 1. 122-1978. Development of Floor Design Response Spectra for Seismic Design of Floor-supported Equipment or Components[S].
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