基于有效分区的核电蒸汽发生器传热计算方法
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摘要
针对现有立式U型管蒸汽发生器,将U型管分为直管和U型管两个区段,基于分区思路提出了一种总传热面积的新计算方法。通过公式选取和介质定性温度确定,直管区段作为设备换热面积由传热计算得出,U型管段作为堵管面积余量由其结构尺寸确定,最终计算出总传热面积。该方法计算准确,在满足换热安全余量条件下兼顾经济性。按此方法,对AP1000和EPR项目的蒸汽发生器进行了对比分析,总传热面积计算值与两个项目总传热面积值的相对误差小于1%,表明该计算方法可行且准确。
To calculate the heat transfer of the vertical U-Bend tubes steam generator at present,a new calculation method is discussed in this article. The U-bend tubes are first divided into U-bend part and straight part. The area of straight tubes as heat transfer area is calculated by the choice formulas and the definition of characteristic temperature for fluid property. The area of U-bend tubes as plugged area allowance is confirmed by itself structure,and the all heat transfer area is well defined. This presented calculation method has good accuracy and economy while satisfying the safety requirement. By using this method,the total heat-transfer area of two practical cases,AP1000 and EPR,are calculated and compared with the measured data,and the results determined from others' published methods. The relative errors of the overall heat exchange area are less than 1%. It indicates that the proposed calculation method is feasible and accurate.
To calculate the heat transfer of the vertical U-Bend tubes steam generator at present,a new calculation method is discussed in this article. The U-bend tubes are first divided into U-bend part and straight part. The area of straight tubes as heat transfer area is calculated by the choice formulas and the definition of characteristic temperature for fluid property. The area of U-bend tubes as plugged area allowance is confirmed by itself structure,and the all heat transfer area is well defined. This presented calculation method has good accuracy and economy while satisfying the safety requirement. By using this method,the total heat-transfer area of two practical cases,AP1000 and EPR,are calculated and compared with the measured data,and the results determined from others' published methods. The relative errors of the overall heat exchange area are less than 1%. It indicates that the proposed calculation method is feasible and accurate.
引文
[1] 丁训慎.压水堆核电站蒸汽发生器传热特性的试验研究[J]. 核科学与工程,1989,9(3):219-225.DING Xun-shen.The testing research for heat transfer characteristics of PWR steam generators [J]. Chinese Journal of Nuclear Science and Engineering,1989,9(3):219-225.
[2] 甘建衡.秦山核电二期工程蒸汽发生器的设计特点[J]. 核动力工程,1995,16(1):18-22.GAN Jian-heng. Design characteristic of steam generator Qinshan-Ⅱ[J]. Nuclear Power Engineering,1995,16(1):18-22.
[3] 熊扬恒.核电站蒸汽发生器研究设计中的几个问题[J]. 核动力工程,1994,15(4):319-333.XIONG Yang-heng. Several problems in the research and design to the steam generator of the nuclear power plant[J]. Nuclear Power Engineering,1994,15(4):319-333.
[4] 罗明坤,王飞,黄伟,等.立式U型管自然循环蒸汽发生器传热面积的近似理论计算公式[J].核动力工程,2001,22(3):221-225.LUO Ming-kun,WANG Fei,HUANG Wei et al. Kind of approximate theoretical calculating formula of heat-exchange area for the vertical U-bend tube natural-circuit steam generator [J]. Nuclear Power Engineering,2001,22(3):221-225.
[5] 钱颂文.换热器设计手册[M].北京:化学工业出版社,2002.QIAN Song-wen. Heat-exchanger design manual [M]. Beijing:Chemical Industrial Press,2002.
[6] 沈自求.沸腾传热研究[J].大连理工大学学报,2001,41(3):253-259.SHEN Zi-qiu. Study of boiling heat transfer[J].Journal of Dalian University of Technology,2001,41(3):253-259.
[7] 王成龙,从腾龙,王泽勇,等.蒸汽发生器传热管一、二次侧耦合换热及管外过冷沸腾数值研究[J].原子能科学技术,2014,48(4):610-616.WANG Cheng-long,CONG Teng-long,WANG Ze-yong,et al.Numerical investigation of coupled heat transfer between primary and secondary side of SG tube and sub-cooled flow boiling on secondary side[J]. Atomic Energy Sicence and Technology,2014,48(4):610-616.
[8] 熊健,付龙舟.核蒸汽发生器建模及其仿真[J].核科学与工程,1989,9(1):20-33.XIONG Jian,FU long-zhou,Dynamicmodeling and simulation of a nuclear steam generator[J].Chinese Journal of Nuclear Science and Engineering,1989,9(1):20-33.
[9] 孟剑,徐金康.AP1000反应堆蒸汽发生器的设计特点[J].发电设备,2015,29(1):35-39.MENG Jian,XU Jin-kang. Design Features of the AP1000 PWR Steam Generator[J]. Power Equipment,2015,29(1):35-39.
[10] 姚彦贵,唐琦琳,王经.核电蒸汽发生器热工水力静态特性计算分析研究[J].能源技术,2017,28(2):63-69.YAO Yan-gui,TANG Qi-lin,WANG Jing.Study of nuclear thermal hydraulic static characteristic calculation andlysis[J].Enercy Tcehnology,2017,28(2):63-69.
[11] 展锦程.核电厂立式自然循环蒸汽发生器数学模型的建立[J].广东电力,2000,13(6):7-9.ZHAN Jin-cheng. Mathematical modeling of vertical natural circulation type steam generators in nuclear power plants[J].Guangdong Electric Power,2000,13(6):7-9.
[12] 李宇,周涛,刘亮,等.AP1000与二代核电蒸汽发生器传热特性对比研究[J].华电技术,2015,37(10):69-75.LI Yu,ZHOU Tao,LIU Liang,et al.Comparative researches on the heat transfer characteristics of the SG between AP1000 and 2rd generation nuclear power plant[J].Huadian Technology,2015,37(10):69-75.
[13] 施明恒,甘永平,马重芳.沸腾和凝结[M].河北:高等教育出版社,1995.SHI Ming-heng,GAN Yong-ping,MA Chong-fang. Boiling and condensation heat transfer[M] Hebei: High Education Press,1995.
[14] 鲁钟琪.两相流与沸腾传热[M].北京:清华大学出版社,2002.LU Zhong-qi. Two-phase flow and boiling heat transfer.[M]Beijing:Tsinghua University Press,2002.
[15] 丁训慎.立式自然循环蒸汽发生器的传热特性及其计算[J].核动力工程,1982,3(6):37-46.DING Xun-shen. Heattransfer characteristic and calculation of vertical natural circulation steam generator [J].Nuclear Power Engineering,1982,3(6):37-46.
[16] GB/T 151-2014 热交换器[S].北京:中国标准出版社,2015:118-120.GB/T 151-2014 Heat exchangers [S]. Beijing:China Standard Press,2015:118-120.
[17] 林诚格,郁祖盛,欧阳予.非能动安全先进压水堆核电技术(上)[M].北京:原子能出版社,2010.LIN Cheng-ge,YU Zu-sheng,OU Yang-yu. Passivesafe advanced PWR technology (Ⅰ)[M]. Beijing:Atom Energy Press,2010.
[18] 王巍. AP1000蒸汽发生器换热面积计算探讨[J].东方电气评论,2013,27(1):53-55,74.WANG Wei. Calculation of heat transfer area for AP1000 steam generator [J].Dongfang Electric Review,2013,27(1):53-55,74.
[2] 甘建衡.秦山核电二期工程蒸汽发生器的设计特点[J]. 核动力工程,1995,16(1):18-22.GAN Jian-heng. Design characteristic of steam generator Qinshan-Ⅱ[J]. Nuclear Power Engineering,1995,16(1):18-22.
[3] 熊扬恒.核电站蒸汽发生器研究设计中的几个问题[J]. 核动力工程,1994,15(4):319-333.XIONG Yang-heng. Several problems in the research and design to the steam generator of the nuclear power plant[J]. Nuclear Power Engineering,1994,15(4):319-333.
[4] 罗明坤,王飞,黄伟,等.立式U型管自然循环蒸汽发生器传热面积的近似理论计算公式[J].核动力工程,2001,22(3):221-225.LUO Ming-kun,WANG Fei,HUANG Wei et al. Kind of approximate theoretical calculating formula of heat-exchange area for the vertical U-bend tube natural-circuit steam generator [J]. Nuclear Power Engineering,2001,22(3):221-225.
[5] 钱颂文.换热器设计手册[M].北京:化学工业出版社,2002.QIAN Song-wen. Heat-exchanger design manual [M]. Beijing:Chemical Industrial Press,2002.
[6] 沈自求.沸腾传热研究[J].大连理工大学学报,2001,41(3):253-259.SHEN Zi-qiu. Study of boiling heat transfer[J].Journal of Dalian University of Technology,2001,41(3):253-259.
[7] 王成龙,从腾龙,王泽勇,等.蒸汽发生器传热管一、二次侧耦合换热及管外过冷沸腾数值研究[J].原子能科学技术,2014,48(4):610-616.WANG Cheng-long,CONG Teng-long,WANG Ze-yong,et al.Numerical investigation of coupled heat transfer between primary and secondary side of SG tube and sub-cooled flow boiling on secondary side[J]. Atomic Energy Sicence and Technology,2014,48(4):610-616.
[8] 熊健,付龙舟.核蒸汽发生器建模及其仿真[J].核科学与工程,1989,9(1):20-33.XIONG Jian,FU long-zhou,Dynamicmodeling and simulation of a nuclear steam generator[J].Chinese Journal of Nuclear Science and Engineering,1989,9(1):20-33.
[9] 孟剑,徐金康.AP1000反应堆蒸汽发生器的设计特点[J].发电设备,2015,29(1):35-39.MENG Jian,XU Jin-kang. Design Features of the AP1000 PWR Steam Generator[J]. Power Equipment,2015,29(1):35-39.
[10] 姚彦贵,唐琦琳,王经.核电蒸汽发生器热工水力静态特性计算分析研究[J].能源技术,2017,28(2):63-69.YAO Yan-gui,TANG Qi-lin,WANG Jing.Study of nuclear thermal hydraulic static characteristic calculation andlysis[J].Enercy Tcehnology,2017,28(2):63-69.
[11] 展锦程.核电厂立式自然循环蒸汽发生器数学模型的建立[J].广东电力,2000,13(6):7-9.ZHAN Jin-cheng. Mathematical modeling of vertical natural circulation type steam generators in nuclear power plants[J].Guangdong Electric Power,2000,13(6):7-9.
[12] 李宇,周涛,刘亮,等.AP1000与二代核电蒸汽发生器传热特性对比研究[J].华电技术,2015,37(10):69-75.LI Yu,ZHOU Tao,LIU Liang,et al.Comparative researches on the heat transfer characteristics of the SG between AP1000 and 2rd generation nuclear power plant[J].Huadian Technology,2015,37(10):69-75.
[13] 施明恒,甘永平,马重芳.沸腾和凝结[M].河北:高等教育出版社,1995.SHI Ming-heng,GAN Yong-ping,MA Chong-fang. Boiling and condensation heat transfer[M] Hebei: High Education Press,1995.
[14] 鲁钟琪.两相流与沸腾传热[M].北京:清华大学出版社,2002.LU Zhong-qi. Two-phase flow and boiling heat transfer.[M]Beijing:Tsinghua University Press,2002.
[15] 丁训慎.立式自然循环蒸汽发生器的传热特性及其计算[J].核动力工程,1982,3(6):37-46.DING Xun-shen. Heattransfer characteristic and calculation of vertical natural circulation steam generator [J].Nuclear Power Engineering,1982,3(6):37-46.
[16] GB/T 151-2014 热交换器[S].北京:中国标准出版社,2015:118-120.GB/T 151-2014 Heat exchangers [S]. Beijing:China Standard Press,2015:118-120.
[17] 林诚格,郁祖盛,欧阳予.非能动安全先进压水堆核电技术(上)[M].北京:原子能出版社,2010.LIN Cheng-ge,YU Zu-sheng,OU Yang-yu. Passivesafe advanced PWR technology (Ⅰ)[M]. Beijing:Atom Energy Press,2010.
[18] 王巍. AP1000蒸汽发生器换热面积计算探讨[J].东方电气评论,2013,27(1):53-55,74.WANG Wei. Calculation of heat transfer area for AP1000 steam generator [J].Dongfang Electric Review,2013,27(1):53-55,74.