【摘要】：本文選取重大專(zhuān)項(xiàng)綜合性能試驗(yàn)開(kāi)展的主蒸汽管道斷裂事故全過(guò)程瞬態(tài)模擬工況作為基準(zhǔn)工況,應(yīng)用GOTHIC程序進(jìn)行了詳細(xì)的三維建模,模擬了試驗(yàn)殼大空間和熱阱儲(chǔ)熱、蒸汽在殼體內(nèi)壁面冷凝、殼體外壁面水膜蒸發(fā)等傳熱傳質(zhì)過(guò)程。通過(guò)對(duì)比試驗(yàn)數(shù)據(jù)和程序計(jì)算結(jié)果,研究試驗(yàn)殼大空間的熱工響應(yīng)特性和程序模型的適用性。研究結(jié)果表明:程序模型能很好地分析試驗(yàn)殼溫度、壓力變化趨勢(shì),尤其是在蒸汽大流量噴放后階段,程序分析結(jié)果和試驗(yàn)結(jié)果符合很好。另外,噴口的射流類(lèi)型會(huì)顯著影響大空間溫度分層現(xiàn)象,進(jìn)而影響蒸汽在試驗(yàn)殼體內(nèi)壁面的冷凝過(guò)程。該研究結(jié)果可為后續(xù)應(yīng)用GOTHIC程序分析非能動(dòng)核電廠安全殼響應(yīng)的可行性提供參考和借鑒。
[Abstract]:In this paper, the transient simulation condition of the whole process of the main steam pipeline fracture accident is selected as the reference condition, and the detailed three-dimensional modeling is carried out by using the GOTHIC program, and the large space and heat trap heat storage in the test shell are simulated. The steam condenses on the inner wall of the shell and evaporates the water film on the outer wall of the shell. The characteristics of thermal response and the applicability of the program model in large space of the test shell are studied by comparing the experimental data with the results of the program calculation. The results show that the program model can well analyze the temperature and pressure change trend of the test shell, especially in the stage of large steam discharge, the results of the program analysis are in good agreement with the test results. In addition, the jet type of nozzle will significantly affect the phenomenon of temperature stratification in large space, and further affect the condensation process of steam on the inner wall of the test shell. The results can be used for reference in the analysis of containment response of inactive nuclear power plants using GOTHIC program.
【作者單位】： 上海核工程研究設(shè)計(jì)院;
【分類(lèi)號(hào)】：TL364.4
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本文編號(hào)：2284290