本文選題：超臨界水 + 類三角形子通道��； 參考：《華北水利水電大學(xué)》2015年碩士論文

【摘要】：超臨界水冷堆(Supercritical water cooled reactor-SCWR)是第四代先進(jìn)核能系統(tǒng),是GIF重點(diǎn)研發(fā)第四代堆型。反應(yīng)堆熱工水力是SCWR研發(fā)基礎(chǔ),論文重點(diǎn)針對(duì)反應(yīng)堆堆芯類三角形子通道內(nèi)流動(dòng)傳熱特性,開展試驗(yàn)研究,為SCWR熱工準(zhǔn)則和安全設(shè)計(jì)提供試驗(yàn)數(shù)據(jù)和傳熱特性預(yù)測方法,具有極其重要的工程應(yīng)用價(jià)值和理論意義。論文在熱流密度為200~800 k W/m2,壓力為23~28 MPa,質(zhì)量流速為700~1300kg/(m2·s)的參數(shù)范圍,對(duì)棒徑為8 mm,柵距比為1.4的SCWR類三角形子通道,進(jìn)行了超臨界水的流動(dòng)傳熱試驗(yàn)研究。研究獲得了類三角形子通道的軸向溫度分布和典型傳熱特性,研究了參數(shù)對(duì)傳熱特性的影響,擬合出預(yù)測類三角形子通道內(nèi)超臨界水傳熱特性的試驗(yàn)關(guān)聯(lián)式,并將試驗(yàn)數(shù)據(jù)與經(jīng)典關(guān)聯(lián)式進(jìn)行了對(duì)比分析。SCWR類三角形子通道內(nèi)超臨界水的傳熱特性試驗(yàn)的研究表明,類三角形子通道軸向壁溫沿流動(dòng)方向逐漸升高,在大比熱區(qū)(cp8.4 k J/(kg·K))壁溫平緩,傳熱系數(shù)出現(xiàn)峰值,發(fā)生了傳熱強(qiáng)化。在壓力和質(zhì)量流速相同時(shí),壁面溫度隨熱流密度的增加而升高,傳熱系數(shù)峰值降低。而在質(zhì)量流速和熱流密度相同時(shí),壁面溫度隨壓力提高而增大,換熱系數(shù)峰值減小。質(zhì)量流速可以強(qiáng)化傳熱,質(zhì)量流速增大,壁溫降低換熱系數(shù)增大。在遠(yuǎn)離大比熱區(qū)的低焓值區(qū)熱流密度和壓力對(duì)傳熱的影響較小。而在大比熱區(qū)內(nèi),傳熱系數(shù)受熱流密度和壓力的影響顯著。傳熱系數(shù)峰值隨熱流密度和壓力的增大而明顯降低。隨焓值增加,越過大比熱區(qū)時(shí),熱流密度和壓力和質(zhì)量流速對(duì)傳熱系數(shù)的影響減小。試驗(yàn)研究還發(fā)現(xiàn),當(dāng)熱流密度達(dá)到800 k W/m2時(shí),壁溫和傳熱系數(shù)表現(xiàn)出了異常規(guī)律,在大比熱區(qū),壁溫不再隨焓值平坦變化,換熱系數(shù)峰值不明顯。當(dāng)壓力提高到28 MPa時(shí),在大比熱區(qū)的強(qiáng)化傳熱作用被削弱。質(zhì)量流速提高到一定程度時(shí),其傳熱強(qiáng)化作用效果不如在低質(zhì)量流速時(shí)明顯。基于類三角形子通道內(nèi)超臨界水傳熱特性試驗(yàn)數(shù)據(jù),擬合針對(duì)類三角形子通道中在超臨界壓力下遠(yuǎn)離大比熱區(qū)高焓值區(qū)域和低焓值區(qū)的試驗(yàn)關(guān)聯(lián)式,兩個(gè)擬合關(guān)聯(lián)式計(jì)算值與試驗(yàn)數(shù)據(jù)吻合的比較好。在與常用超臨界傳熱經(jīng)驗(yàn)關(guān)聯(lián)式的對(duì)比中,所選五組經(jīng)典關(guān)聯(lián)式的預(yù)測結(jié)果較試驗(yàn)結(jié)果偏大,整體預(yù)測存在偏差。Jackson公式和Bishop預(yù)測數(shù)值整體上與試驗(yàn)數(shù)據(jù)吻合稍好。本研究得到國家自然基金NO.5146026和河南高校創(chuàng)新人才NO.2012HASTIT018的資助。
[Abstract]:The supercritical water cooled reactor (Supercritical water cooled reactor-SCWR) is the fourth generation advanced nuclear energy system. It is the focus of the research and development of the fourth generation reactor. The thermal hydraulic power of the reactor is the foundation of SCWR research and development. The paper focuses on the flow and heat transfer characteristics in the triangle subchannel of the reactor core, open and open the test and study for the SCWR thermal criterion and the safety design. The method for prediction of test data and heat transfer characteristics is of great importance in engineering application and theoretical significance. In this paper, the flow transmission of supercritical water is carried out in the heat flow density of 200~800 K W/m2, pressure of 23~28 MPa, mass velocity of 700~1300kg/ (M2 s), and SCWR type triangle subchannel with a diameter of 8 mm and a distance ratio of 1.4. The axial temperature distribution and typical heat transfer characteristics of the sub triangle subchannel are obtained. The influence of the parameters on the heat transfer characteristics is studied. The experimental correlations for the prediction of the heat transfer characteristics of the supercritical water in the triangle subchannel are fitted, and the experimental data are compared with the classical correlation to analyze the.SCWR triangle subtypes. The study on the heat transfer characteristic test of the super critical water in the channel shows that the wall temperature of the sub - channel axis increases gradually along the flow direction, and the wall temperature is gentle in the large specific heat zone (cp8.4 K J/ (kg. K)), the heat transfer coefficient has a peak value, and the heat transfer intensification occurs. When the mass velocity and the heat flux are the same, the wall temperature increases with the pressure, and the peak value of the heat transfer coefficient decreases. The mass velocity can strengthen the heat transfer, the mass velocity increases, the wall temperature decreases and the heat transfer coefficient increases. The heat flow density and pressure in the low enthalpy zone far away from the large specific heat area have little effect on the heat transfer. In the region, the heat transfer coefficient is significantly affected by the heat flux density and pressure. The peak value of heat transfer coefficient decreases obviously with the increase of heat flux and pressure. With the increase of enthalpy, the influence of heat flux and pressure and mass velocity on the heat transfer coefficient decreases with the increase of the enthalpy value. The experimental study is also present, when the heat flux reaches 800 K W/m2, the wall is mild. The heat transfer coefficient shows an abnormal law. In the large specific heat zone, the wall temperature no longer varies with the enthalpy, and the peak value of the heat transfer coefficient is not obvious. When the pressure is raised to 28 MPa, the enhancement of heat transfer is weakened. When the mass velocity is raised to a certain extent, the effect of the heat transfer is not as obvious as at the low mass velocity. Based on the class three The experimental data of the supercritical water heat transfer characteristics in the angular subchannel are fitted to the experimental correlations between the high enthalpy region and the low enthalpy zone in the super critical pressure region under the supercritical pressure. The calculated values of the two fitting correlations are in good agreement with the experimental data. In comparison with the commonly used empirical correlations for the common supercritical heat transfer, The results of the selected five groups of classic correlations are larger than those of the test results. The overall prediction has a deviation.Jackson formula and the Bishop prediction value is in good agreement with the experimental data. This study is supported by the national natural fund NO.5146026 and the innovative talents NO.2012HASTIT018 of Henan University.
【學(xué)位授予單位】：華北水利水電大學(xué)
【學(xué)位級(jí)別】：碩士
【學(xué)位授予年份】：2015
【分類號(hào)】：TK124

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本文編號(hào)：1952705