本文關(guān)鍵詞： 波動管 熱震蕩 疲勞分析　出處：《應用數(shù)學和力學》2014年S1期 　論文類型：期刊論文

【摘要】：典型的管道分析會對所有預期的熱載荷進行評估,研究表明核電廠穩(wěn)壓器波動管會經(jīng)受非預期的并伴隨熱分層現(xiàn)象產(chǎn)生的熱震蕩載荷。利用理論分析方法推導出便于求解的半解析公式,并對其進行了工程實例驗證,從而驗證推導的半解析公式的正確性。同時采用半解析公式評估了核電廠典型的穩(wěn)壓器波動管在熱分層溫差不同時熱震蕩載荷導致管道內(nèi)壁產(chǎn)生的局部峰值應力,并根據(jù)ASME規(guī)范評估了穩(wěn)壓器波動管熱震蕩應力對管道疲勞的影響。研究結(jié)果表明,核電廠在升溫或停堆期間熱震蕩載荷對波動管的疲勞使用系數(shù)影響較小;在核電廠長時間的正常運行期間,當穩(wěn)壓器波動管橫截面垂直方向的溫差達到臨界值時,熱震蕩載荷對波動管的疲勞使用系數(shù)影響非常顯著。
[Abstract]:A typical pipeline analysis evaluates all expected thermal loads, The study shows that the fluctuating tube of the voltage regulator of nuclear power plant will undergo unexpected thermal shock load caused by thermal stratification. The semi-analytical formula is derived by using the theoretical analysis method and verified by an engineering example. At the same time, the semi-analytical formula is used to evaluate the local peak stress on the inner wall of the pipe caused by the thermal stratification temperature difference at the same time, and the semi-analytical formula is used to evaluate the local peak stress of the typical pressurizer fluctuating tube of the nuclear power plant at the same time of the thermal stratification temperature difference. According to the ASME code, the influence of thermal oscillation stress on pipe fatigue is evaluated. The results show that the thermal oscillation load has little effect on the fatigue coefficient of the fluctuating tube during the heating or shutdown period of the nuclear power plant. During a long period of normal operation of the nuclear power plant, when the temperature difference in the vertical direction of the fluctuating tube reaches the critical value, the thermal oscillation load has a very significant effect on the fatigue coefficient of the fluctuating tube.
【作者單位】： 中國核動力研究設(shè)計院核反應堆系統(tǒng)設(shè)計技術(shù)重點實驗室;
【分類號】：TM623

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本文編號：1535643