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CPR1000反应堆发生全失流事故后,冷却剂流量迅速下降,一回路温度和压力升高,可能导致堆芯发生偏离泡核沸腾(DNB)的危险。本文使用中广核自主开发的系统程序GINKGO和子通道程序LINDEN分别对CPR1000的电厂系统和堆芯部件进行了建模,再使用GINKGO进行系统分析、LINDEN根据系统分析结果进行子通道分析后确定偏离泡核沸腾比(DNBR)达到最小值的时刻,并在该时刻使用抽样统计方法对部分相关输入参数进行不确定性分析,同时考虑系统程序、子通道程序以及CHF关系式的不确定性,最终得到满足双95下的最小偏离泡核沸腾比(MDNBR)。结果表明:CPR1000全失流事故进程中,并未发生DNB,且具有较大裕量,同时也证明将抽样统计应用到CPR1000全失流事故分析中是可行的。 相似文献
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To investigate the steady thermal hydraulic characteristics of U-tube steam generator(SG), a 1D simulation code based on the four-equation drift flux model is developed. The U-tube channels presumably consist mainly of the primary channel, secondary channel, and tube wall. In the sub-cooling regions of the primary and secondary channels, flow is simulated using the single-phase flow model, whereas that in the boiling regions of the secondary channels is simulated using the four-equation drift flux model. The first-order equations of upwind difference are derived based on the staggered grid. Steady-state thermal hydraulic parameters are obtained with a cross-iteration scheme of heat balance and natural circulation requirement. The developed code is applied to analyze the SG behavior of the Qinshan I Nuclear Power Plant under 100%, 75%, 50%, 30%, and 15% power conditions. Analysis results are then compared with the simulation results obtained using RELAP5. 相似文献
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通过调整压水堆(PWR,Pressurized Water Reactor)运行期间各种水化学参数,能够有效控制一回路水质。作为影响燃料性能的重要因素,污垢(CRUD,Chalk Rivers Unidentified Deposits)在燃料表面的沉积行为会随水化学参数调整而改变。本文研究了溶解氢气(DH,Dissolved Hydrogen)浓度、pH、注锌和超声波清洗(UFC,Ultrasonic Fuel Cleaning)对某PWR功率运行期间CRUD沉积过程的影响,结果表明DH浓度对CRUD沉积影响较小,提高pH、注锌和应用UFC能够抑制CRUD沉积。研究成果为从水化学控制角度提高PWR安全性和经济性提供了理论依据和数据支撑。 相似文献
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