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失水事故中反應(yīng)堆堆芯再淹沒數(shù)學(xué)模型

發(fā)布時(shí)間:2018-05-29 11:58

  本文選題:壓水堆 + 失水事故; 參考:《核科學(xué)與工程》1999年01期


【摘要】:在分析和比較前人現(xiàn)有工作的基礎(chǔ)上,提出了一個(gè)新的失水事故后堆芯底部再淹沒過程的再潤(rùn)濕模型。本模型分別采用了考慮夾帶的兩流體方程和二維導(dǎo)熱方程來描述兩相流熱工水力特性和壁面導(dǎo)熱特性。這個(gè)模型的特點(diǎn)是定義了一個(gè)聚冷前沿附近的過渡區(qū)傳熱,,從而回避了采用至今仍很容易混淆的驟冷溫度、淬火溫度和Leidenfrost溫度,便于工程應(yīng)用。在經(jīng)過進(jìn)一步驗(yàn)證之后,該模型將補(bǔ)充到TRAC程序中,擴(kuò)充其預(yù)測(cè)能力。
[Abstract]:Based on the analysis and comparison of the previous work, a new rewetting model for the reflooding process of the core bottom after a loss of water accident is proposed. In this model, two fluid equations with entrainment and two dimensional heat conduction equations are used to describe the thermohydraulic and wall thermal conductivity of two-phase flow respectively. This model is characterized by the definition of heat transfer in a transition zone near the condensation front, thus avoiding the use of quenching temperature, quenching temperature and Leidenfrost temperature, which are still easily confused up to now, which is convenient for engineering application. After further verification, the model will be added to the TRAC program to expand its prediction ability.
【作者單位】: 西安交通大學(xué)核能與熱能工程系 日本京都大學(xué)反應(yīng)堆研究所
【分類號(hào)】:O141.4,O141.4


本文編號(hào):1950801

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