本文選題：液態(tài)燃料熔鹽堆 + RELAP5　； 參考：《中國(guó)科學(xué)院研究生院(上海應(yīng)用物理研究所)》2017年博士論文

【摘要】：熔鹽堆是第四代先進(jìn)核能系統(tǒng)之一,具有良好的經(jīng)濟(jì)性、固有安全性、在線加料以及在線后處理優(yōu)勢(shì)。液態(tài)燃料熔鹽堆的核燃料是作為液體在一回路中流動(dòng),這就使得液態(tài)燃料熔鹽堆的中子物理和熱工水力特性不同于傳統(tǒng)的固態(tài)燃料反應(yīng)堆。反應(yīng)堆安全問題是核工程發(fā)展最重要的研究課題,安全分析的任務(wù)是研究不同工況下反應(yīng)堆的安全性,是反應(yīng)堆設(shè)計(jì)和建造過程中的一項(xiàng)重要內(nèi)容。開發(fā)液態(tài)燃料熔鹽堆系統(tǒng)安全分析程序和構(gòu)建液態(tài)燃料熔鹽堆安全評(píng)估準(zhǔn)則是反應(yīng)堆安全分析的重要基礎(chǔ),對(duì)于保障和提高反應(yīng)堆安全性和可靠性具有重要的意義。本論文基于液態(tài)燃料熔鹽堆點(diǎn)堆動(dòng)力學(xué)模型、熱工水力模型和時(shí)滯方程組的求解算法,對(duì)RELAP5/MOD4.0程序進(jìn)行功能擴(kuò)展,并采用美國(guó)橡樹嶺國(guó)家實(shí)驗(yàn)室(ORNL)熔鹽實(shí)驗(yàn)堆(MSRE)啟泵、停泵、自然循環(huán)和功率提升瞬態(tài)過程實(shí)驗(yàn)數(shù)據(jù)驗(yàn)證了模型和程序的正確性,為液態(tài)燃料熔鹽堆安全分析提供了工具支持。同時(shí),依據(jù)國(guó)內(nèi)HAF、HAD法規(guī)標(biāo)準(zhǔn)以及國(guó)際上IAEA、NRC和ORNL的相關(guān)評(píng)估報(bào)告,參考?jí)核�、鈉冷快堆、高溫氣冷堆的始發(fā)事件分類方法,對(duì)液態(tài)燃料熔鹽堆的始發(fā)事件進(jìn)行了分類;根據(jù)反應(yīng)堆材料的屬性,確定了液態(tài)燃料熔鹽堆的安全限值;采用考慮不確定度的保守單通道熱管評(píng)估模型,獲得堆芯燃料熔鹽和石墨慢化劑的最高溫度,構(gòu)建了液態(tài)燃料熔鹽堆安全評(píng)估準(zhǔn)則,為液態(tài)燃料熔鹽堆的安全分析奠定基礎(chǔ)。為進(jìn)一步驗(yàn)證擴(kuò)展的液態(tài)燃料熔鹽堆系統(tǒng)分析程序和安全評(píng)估準(zhǔn)則的適用性,分別對(duì)小功率2 MWt熔鹽實(shí)驗(yàn)堆TMSR-LF1和大功率2250 MWt熔鹽增殖堆MSBR系統(tǒng)進(jìn)行安全特性的研究,計(jì)算了在反應(yīng)性瞬態(tài)、二回路排熱量減小、二回路排熱量增加工況下的反應(yīng)堆瞬態(tài)響應(yīng),得出了反應(yīng)堆在不同工況下的安全特性。計(jì)算結(jié)果顯示,TMSR-LF1的安全裕度大于MSBR。TMSR-LF1在控制棒失控抽出、二回路熔鹽失流工況下反應(yīng)堆的溫度會(huì)超出安全限值范圍,而MSBR在控制棒失控插入、加料過程中意外超臨界、冷卻熔鹽失流、負(fù)載功率增加工況下溫度會(huì)超出安全限值范圍,需要及時(shí)采取措施以免反應(yīng)堆的損毀。分析結(jié)果表明,擴(kuò)展的RELAP5/MOD4.0程序和構(gòu)建的安全評(píng)估準(zhǔn)則適用于不同功率的液態(tài)熔鹽堆安全評(píng)估分析�；赗ELAP5/MOD4.0的液態(tài)燃料熔鹽堆系統(tǒng)分析程序的開發(fā)、安全評(píng)估準(zhǔn)則的構(gòu)建以及它們的應(yīng)用分析,對(duì)中國(guó)科學(xué)院先進(jìn)核能創(chuàng)新研究院液態(tài)燃料熔鹽堆的進(jìn)一步工程設(shè)計(jì)和安全分析具有重要的工程參考價(jià)值。
[Abstract]:Molten salt reactor is one of the fourth generation advanced nuclear power systems, which has the advantages of good economy, inherent safety, on-line feeding and on-line post-processing. The nuclear fuel of liquid fuel molten salt reactor flows in a loop as a liquid, which makes the neutron physical and thermohydraulic characteristics of liquid fuel molten salt reactor different from those of conventional solid fuel reactor. Reactor safety is one of the most important research topics in the development of nuclear engineering. The task of safety analysis is to study the safety of reactors under different conditions, and it is an important content in the process of reactor design and construction. The development of safety analysis program for liquid fuel molten salt reactor system and the construction of safety assessment criteria for liquid fuel molten salt reactor are the important basis of reactor safety analysis, which is of great significance to ensure and improve the safety and reliability of the reactor. Based on the solution algorithm of liquid fuel molten salt reactor dynamic model, thermohydraulic model and time-delay equations, this paper extends the function of RELAP5/MOD4.0 program, and uses Oak Ridge National Laboratory (Oak Ridge National Laboratory) MSRE) start-up pump to stop the pump. The experimental data of natural cycle and power boost transient process verify the correctness of the model and program, and provide a tool support for the safety analysis of liquid fuel molten salt reactor. At the same time, according to the domestic Hafer had code standard and the international IAEAA NRC and ORNL evaluation reports, referring to the classification method of the origin events of PWR, NRC and HTGR, the initial events of liquid fuel molten salt reactor are classified. According to the properties of reactor materials, the safety limit of liquid fuel molten salt reactor is determined, and the maximum temperature of core fuel molten salt and graphite moderator is obtained by using a conservative single-channel heat pipe evaluation model considering uncertainty. The safety evaluation criteria of liquid fuel molten salt reactor are established, which lays a foundation for the safety analysis of liquid fuel molten salt reactor. In order to further verify the applicability of the extended liquid fuel molten salt reactor system analysis program and safety evaluation criteria, the safety characteristics of the low power 2 MWt molten salt test reactor (TMSR-LF1) and the high power 2250 MWt molten salt breeder (MSBR) system were studied, respectively. The transient response of the reactor under the condition of reactive transient, the secondary loop heat emission decreases and the secondary loop heat emission increases is calculated, and the safety characteristics of the reactor under different operating conditions are obtained. The calculation results show that the safety margin of TMSR-LF1 is greater than that of MSBR.TMSR-LF1 when the control rod is out of control, the temperature of the reactor will exceed the safety limit under the secondary loop molten salt loss condition, and the MSBR is inserted out of control control rod and accidentally supercritical during the feeding process. When the cooling molten salt is out of current, the temperature will exceed the safety limit under the condition of increasing load power, so it is necessary to take measures in time to avoid the reactor damage. The analysis results show that the extended RELAP5/MOD4.0 program and the constructed safety evaluation criteria are suitable for the safety assessment analysis of liquid molten salt reactor with different power. The development of liquid fuel molten salt reactor system analysis program based on RELAP5/MOD4.0, the construction of safety evaluation criteria and their application analysis, It has important engineering reference value for further engineering design and safety analysis of liquid fuel molten salt reactor in Advanced Nuclear Energy Innovation Research Institute of Chinese Academy of Sciences.
【學(xué)位授予單位】：中國(guó)科學(xué)院研究生院(上海應(yīng)用物理研究所)
【學(xué)位級(jí)別】：博士
【學(xué)位授予年份】：2017
【分類號(hào)】：TL426

【相似文獻(xiàn)】

相關(guān)期刊論文 前6條

1 ;科學(xué)家研制新型催化劑讓二氧化碳變成低成本液態(tài)燃料[J];廣西科學(xué);2011年03期

2 ;新催化劑讓二氧化碳變身低成本液態(tài)燃料[J];廣西節(jié)能;2011年03期

3 貴大勇,馮順山,劉吉平;高威力FAE液態(tài)燃料的優(yōu)化選擇[J];火炸藥學(xué)報(bào);2002年03期

4 ;節(jié)能減排新技術(shù)集錦[J];技術(shù)與市場(chǎng);2011年05期

5 賀亮;購(gòu)買轉(zhuǎn)讓專利技術(shù)慎防上當(dāng)[J];中國(guó)能源;1999年06期

6 ;[J];;年期

相關(guān)會(huì)議論文 前1條

1 劉國(guó)亮;洪昕林;曾適之;;不同形貌CdS半導(dǎo)體材料的制備[A];第十四屆全國(guó)青年催化學(xué)術(shù)會(huì)議會(huì)議論文集[C];2013年

相關(guān)重要報(bào)紙文章 前1條

1 美國(guó)《油氣雜志》 唐紹紅 譯;全球液態(tài)燃料市場(chǎng)進(jìn)入供求動(dòng)態(tài)變化期[N];中國(guó)石化報(bào);2014年

相關(guān)博士學(xué)位論文 前1條

1 施承斌;液態(tài)燃料熔鹽堆系統(tǒng)分析程序及安全特性研究[D];中國(guó)科學(xué)院研究生院(上海應(yīng)用物理研究所);2017年

，

本文編號(hào)：1788809