铅基堆非能动余热排出系统的设计研究
发布时间：2018-12-06 13:28
【摘要】：铅基堆具有良好的中子学性能、热工水力学性能、化学性能和固有安全特性而成为极具发展潜力的第四代核能系统。在铅基堆停堆后,堆芯活性区产生的大量余热严重威胁着反应堆的安全。铅基堆非能动余热排出系统(PRHRS)的设计研究,对于提高铅基堆在事故工况下的同有安全性,具有重要理论意义和应用价值。本文以1000 MWth铅基堆为研究对象,从铅铋换热模型开发与验证、三种PRHRS的设计与性能分析、参数敏感性分析和性能对比分析四个方面开展了铅基堆PRHRS的设计研究。相关研究成果可为铅基堆非能动余热排出系统的设计提供了经验和参考,对我国自主掌握铅基堆非能动余热排出的关键技术有所借鉴。主要研究成果如下:1)传统压水堆的换热模型不适用于铅铋换热计算,本文基于OECD/NEA LACANES计划中有关铅铋换热的验证工作,在热工水力学分析程序RELAP5/MOD4.0基础上开发了铅铋换热模型,并通过单管测试验证了此铅铋换热模型开发的正确性,建立了铅基堆热工水力学设计与分析的工具基础。2)根据非能动安全设计理念,分别设计了基于蒸汽发生器(SG)、独立热交换器(IHEX)和反应堆容器(RV)的三种PRHRS,并使用RELAP5/MOD 4.0程序分析了全厂断电事故下三种PRHRS的余热排出性能。研究结果表明:基于SG、IHEX和RV的PRHRS余热排出速率分别在事故后0.6 h、5 h和48 h超过堆芯衰变余热,包壳峰值温度分别达到490 ℃、562 ℃和743 ℃,低于包壳温度限值(750 ℃),铅基堆处于安全状态。三种PRHRS均可应对全厂断电这类超设计基准事故,满足设计目标。3)对三种PRHRS参数敏感性进行了分析,研究结果表明:基于SG和IHEX的PRHRS,通过增大换热面积和减小系统响应时间可以增强PRHRS的余热排出性能;而增加冷热芯高度差和减小回路阻力对PRHRS的余热排出性能影响较小。基于RV的PRHRS,通过增大烟囱高度和换热面积、减小间隙宽度可以增强PRHRS的余热排出性能;而增加壁面发射率和减小系统响应时间对PRHRS的余热排出性能影响较小。4)针对三种PRHRS的性能进行对比分析,结果表明:基于SG的PRHRS排热能力最强,更适合用于大功率铅基堆/商业堆,或在事故前期投入运行,带走停堆初期的大量余热;基于IHEX的PRHRS排热能力较强,更适合用于中等功率铅基堆/示范堆,或在事故中期投入运行;而基于RV的PRHRS排热能力较弱,更适合用于小功率铅基堆/研究堆,或作为事故后期长期排热的余热排出系统。同时,在实际铅基堆PRHRS设计中,为提高余热排出的可靠性,建议采取两种以上的非能动余热排出系统。
[Abstract]:Lead based reactor is the fourth generation nuclear power system with great potential for development due to its good neutronic properties, thermal hydraulic properties, chemical properties and inherent safety properties. After the lead-based reactor is shut down, the reactor safety is seriously threatened by a large amount of residual heat generated in the reactor core reactive zone. The design and study of (PRHRS) for lead based reactor passive residual heat removal system is of great theoretical significance and application value for improving the safety of lead based reactor under accident conditions. In this paper, 1000 MWth lead based reactor is taken as the research object. The design and verification of lead bismuth heat transfer model, the design and performance analysis of three kinds of PRHRS, the parameter sensitivity analysis and the performance contrast analysis are carried out. The design and research of lead based reactor PRHRS are carried out. The related research results can provide experience and reference for the design of passive residual heat removal system for lead based reactor, and can be used for reference to master the key technology of passive residual heat removal of lead based reactor in China. The main research results are as follows: 1) the traditional heat transfer model of PWR is not suitable for the calculation of lead and bismuth heat transfer. This paper is based on the verification of lead and bismuth heat transfer in OECD/NEA LACANES plan. A lead bismuth heat transfer model was developed on the basis of thermal hydraulic analysis program RELAP5/MOD4.0, and the correctness of the model was verified by a single tube test. The tool foundation of thermal hydraulics design and analysis for lead based reactor is established. 2) according to the concept of inactive safety design, three kinds of PRHRS, based on (SG), independent heat exchanger (IHEX) and reactor container (RV) are designed, respectively. The residual heat removal performance of three kinds of PRHRS under power failure accident was analyzed by RELAP5/MOD 4.0 program. The results show that the residual heat removal rate of PRHRS based on SG,IHEX and RV exceeds the decay residual heat of core at 0.6 h and 48 h, respectively, and the peak temperature of cladding reaches 490 鈩，
本文编号：2366099
[Abstract]:Lead based reactor is the fourth generation nuclear power system with great potential for development due to its good neutronic properties, thermal hydraulic properties, chemical properties and inherent safety properties. After the lead-based reactor is shut down, the reactor safety is seriously threatened by a large amount of residual heat generated in the reactor core reactive zone. The design and study of (PRHRS) for lead based reactor passive residual heat removal system is of great theoretical significance and application value for improving the safety of lead based reactor under accident conditions. In this paper, 1000 MWth lead based reactor is taken as the research object. The design and verification of lead bismuth heat transfer model, the design and performance analysis of three kinds of PRHRS, the parameter sensitivity analysis and the performance contrast analysis are carried out. The design and research of lead based reactor PRHRS are carried out. The related research results can provide experience and reference for the design of passive residual heat removal system for lead based reactor, and can be used for reference to master the key technology of passive residual heat removal of lead based reactor in China. The main research results are as follows: 1) the traditional heat transfer model of PWR is not suitable for the calculation of lead and bismuth heat transfer. This paper is based on the verification of lead and bismuth heat transfer in OECD/NEA LACANES plan. A lead bismuth heat transfer model was developed on the basis of thermal hydraulic analysis program RELAP5/MOD4.0, and the correctness of the model was verified by a single tube test. The tool foundation of thermal hydraulics design and analysis for lead based reactor is established. 2) according to the concept of inactive safety design, three kinds of PRHRS, based on (SG), independent heat exchanger (IHEX) and reactor container (RV) are designed, respectively. The residual heat removal performance of three kinds of PRHRS under power failure accident was analyzed by RELAP5/MOD 4.0 program. The results show that the residual heat removal rate of PRHRS based on SG,IHEX and RV exceeds the decay residual heat of core at 0.6 h and 48 h, respectively, and the peak temperature of cladding reaches 490 鈩，
本文编号：2366099
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