当前位置:主页 > 科技论文 > 安全工程论文 >

安全壳非能动热量导出系统数值模拟

发布时间:2018-03-05 16:48

  本文选题:非能动 切入点:安全壳冷却系统 出处:《哈尔滨工程大学》2013年硕士论文 论文类型:学位论文


【摘要】:当核反应堆内发生如冷却剂丧失事故(LOCA)和主管道蒸汽破裂事故(MSLB)等严重事故时,安全壳内会由于高温工质(水、水蒸气以及氢气等)的排放而产生升温升压效应,若不及时排除热量,安全壳可能会因超温超压而失效,因此需要设计一个可靠的安全壳热量导出系统。本文中所研究的安全壳热量导出系统采用非能动原理,利用系统回路内冷热流体之间的密度差产生的自然循环驱动力,通过冷凝、对流及沸腾换热的方式,对安全壳内的大气进行降温降压。根据系统配置结构,,可以分为闭式与开式系统,其中闭式系统因系统压力高低可以分为单相和两相系统。 本研究中针对三种不同的热量导出系统,采用C语言自主开发系统的热工水力分析程序PCCS-C,对系统在不同的安全壳内环境条件和不同系统结构条件下进行系统自然循环能力及排热能力的数值模拟计算分析,并根据计算结果对系统进行改进。计算的结果表明,三种系统对事故后安全壳内环境有着良好的自适应性,在一定范围内变化的系统标高差对各系统的自然循环能力和排热能力均无显著影响。 此外,根据各个系统的设计参数和结构参数,采用RELAP5/MOD3.4程序对系统的运行特性和影响因素进行仿真计算与分析,并将计算结果与自主开发的热量导出系统热工水力特性分析程序的结果进行比较。结果表明Relap5对闭式单相系统的计算结果与PCCS-C程序的计算结果能较好的吻合,闭式两相与开式系统的计算结果趋势与PCCS-C程序的结果趋势一致。
[Abstract]:When serious accidents such as loss of coolant and steam rupture in main pipes occur in a nuclear reactor, the pressure rise in containment will be due to the discharge of high temperature working fluids (water, water vapor, hydrogen etc.). If the heat is not eliminated in time, the containment may fail because of overtemperature and overpressure, so it is necessary to design a reliable heat derivation system for containment. The passive principle is used in the heat derivation system of containment studied in this paper. Using the driving force of natural circulation caused by the density difference between the cold and hot fluids in the system loop, the temperature and pressure of the atmosphere in the containment are reduced by means of condensation, convection and boiling heat transfer. According to the configuration of the system, It can be divided into closed system and open system, which can be divided into single phase system and two phase system because of system pressure. In this study, for three different heat transfer systems, The thermal hydraulic analysis program PCCS-Cdeveloped by C language was used to simulate and analyze the natural circulation capacity and heat discharge capacity of the system under different containment environment conditions and different system structure conditions. According to the calculation results, the system is improved. The results show that the three systems have good adaptability to the environment of the containment after the accident. There is no significant effect on the natural circulation capacity and heat removal capacity of each system with the system height difference varying within a certain range. In addition, according to the design parameters and structural parameters of each system, the operating characteristics and influencing factors of the system are simulated and analyzed by RELAP5/MOD3.4 program. The calculated results are compared with the results of the self-developed thermohydraulic analysis program for the heat derived system. The results show that the results of Relap5 for the closed single-phase system are in good agreement with the results of the PCCS-C program. The result trend of closed two phase and open system is consistent with that of PCCS-C program.
【学位授予单位】:哈尔滨工程大学
【学位级别】:硕士
【学位授予年份】:2013
【分类号】:TL364.3

【参考文献】

相关期刊论文 前6条

1 柏平,谭祚;AC-600非能动安全系统设计[J];核动力工程;1989年05期

2 俞冀阳,李坤,贾宝山;AC600非能动安全壳冷却系统长期效应分析[J];核动力工程;2002年03期

3 谭曙时,冷贵君,程旭,倪永君;非能动安全壳冷却系统热工水力单项试验[J];核动力工程;2002年S1期

4 张廷祥,唐宇;非能动安全壳冷却系统水分配装置设计[J];核动力工程;2002年S1期

5 蒋序伦,李忠朋,史重淼,党岩;带喷射泵系统自然循环瞬态特性数值模拟计算[J];核动力工程;1994年02期

6 吴莘馨,姜胜耀,吴少融,张佑杰;喷泉不稳定诱发间歇流量振荡实验研究[J];核动力工程;1997年02期



本文编号:1571090

资料下载
论文发表

本文链接:https://www.wllwen.com/kejilunwen/anquangongcheng/1571090.html


Copyright(c)文论论文网All Rights Reserved | 网站地图 |

版权申明:资料由用户45bd4***提供,本站仅收录摘要或目录,作者需要删除请E-mail邮箱bigeng88@qq.com