【作者】 周翀；

【导师】 杨燕华；

【作者基本信息】 上海交通大学 ， 核能科学与工程， 2013， 博士

【摘要】 系统安全分析程序（以下简称系统程序）是对反应堆系统进行瞬态和事故安全分析的重要工具。在近十年来第四代先进核能系统研发热潮背景下，国际核能界针对第四代反应堆系统程序开展了大量研究工作。由于轻水堆系统程序发展成熟，经过了全面系统的验证和广泛的应用，其中一些被加以修改以适用于第四代核能系统。这些修改后的程序的适用性及可靠性还有待进一步研究。本文针对第四代反应堆中的超临界水冷堆和钠冷快堆进行系统程序的模型开发、验证与应用研究。首先对轻水堆系统程序ATHLET在这两种第四代堆型上的适用性进行评价，在此基础上对ATHLET程序进行二次模型开发，即开发适用于超临界水和钠两种流体的相关计算模型，获得多流体系统程序ATHLET-MF（Multi-Fluid）；其次，对修改后的ATHLET-MF程序进行初步验证，并采用法国PHENIX钠冷快堆的自然对流实验对程序进行评估；最后，将ATHLET-MF程序应用于超临界水冷堆燃料性能验证实验回路的安全分析，并提出对该实验回路的安全系统设计的改进意见。论文的主要工作包括：1. ATHLET程序的适用性评价与多流体模型开发：（1）就ATHLET程序对超临界水冷堆和钠冷快堆的适用性进行分析；（2）增加超临界水的物性计算、传热、压降、临界流模型；（3）增加钠的物性计算、传热、压降模型；（4）引入多流体通用接口，将针对超临界水和钠两种流体的程序扩展整合为多流体模型，获得ATHLET-MF程序版本。2. ATHLET-MF程序多流体模型的初步验证与评估：（1）超临界水冷堆扩展功能的初步验证，包括与理论计算对比、程序比对验证；（2）钠冷快堆扩展功能的评估，即PHENIX反应堆自然对流实验验证。结果表明：ATHLET-MF程序对超临界水冷堆和钠冷快堆系统的瞬态模拟具有良好的适用性和可靠性。3. ATHLET-MF程序多流体模型的应用，即超临界水冷堆燃料性能验证实验回路的安全分析：（1）计算分析了5类设计基准事故，包括冷却剂丧失、主泵卡轴、实验回路断电、冷却剂流道堵塞、以及由于压力管内部构件破裂导致的冷却剂旁流事故；（2）针对初始安全系统设计的缺陷提出改进措施：增加了2个安全信号，提出长期余热排出方案并进行了可行性分析；（3）对安全系统的部分设计参数进行了敏感性分析，提出对安全系统控制信号及设备参数的建议。本文旨在开发和验证适用于超临界水冷堆和钠冷快堆的系统安全分析工具，为超临界水冷堆燃料性能验证实验回路进行安全分析，探索超临界水冷系统的动态和安全特性，提出安全系统设计的改进方向。本文为超临界水冷堆燃料性能验证实验回路的设计和安全许可证申请提供了安全分析工具和分析结果，对该实验回路安全系统的设计具有现实指导意义。更多还原

【Abstract】 System safety analysis code is an important tool to perform transientsand accidents safety analysis for reactor systems. Under the context ofglobal R&D upsurge about Generation IV innovative nuclear systems,plenty of work has been done for Gen-IV reactor system codedevelopment. Because light water reactor system codes are well developedwith systematic V&V and extensive application, some of them aremodified for Gen-IV nuclear systems. However, feasibility and realiabilityof these modified codes are still to be further confirmed.This dissertation aims at development, validation and application ofthe system code for Supercritical water-cooled reactor (SCWR) andSodium-cooled fast reactor (SFR). Firstly, assess the applicability of thelight water reactor system code ATHLET for these two reactor types, anddevelop the multi-fluid model for supercritical water and sodium, to obtainthe system code ATHLET-MF (multi-fluid). Secondly, preliminaryverification of the multi-fluid model and validation with the French SFRPHENIX’s natural convection test. Thirdly, application of theATHLET-MF code to safety analysis and safety system designimprovement of the SCWR Fuel Qualification Test (SCWR-FQT) Loop. The main contents of this dissertation include:1. Applicability assessment of the ATHLET code and development ofthe multi-fluid model.(1) Applicability analysis of the ATHLET code forSCWR and SFR.(2) Implementation of property model, heat transfermodel, pressure drop model and critical flow model for supercritical water.(3) Implementation of property model, heat transfer model and pressuredrop model for sodium.(4) Introduction of the multi-fluid generalinterface to integrate code extensions for supercritical water and sodiuminto the multi-fluid model, and obtain the code version ATHLET-MF.2. Preliminary verification and validation of the multi-fluid model ofthe ATHLET-MF code.(1) Validation of the supercritical watermodifications by comparson with analytical calculation and other codes.(2) Validation of the sodium modifications with the SFR PHENIX naturalconvection test. Results show good applicability and accuration of theATHLET-MF code in transient simulation of SCWR and SFR systems.3. Application of the ATHLET-MF code to safety analysis of theSCWR-FQT loop.(1)5types of design basis accidents are simulated,including loss of coolant accident, primary pump seize, loss of power tothe test loop, blockage of any coolant supply line, and coolant bypassingthe test section due to crack in the internal structures of the pressure tube.(2) Improvement of the initial safety system design,2safety signals areadded, and the long term residual heat removal strategy is proposed and itsfeasibility is analyzed.(3) Sensitivity analysis of some design parametersof the safety system, and suggestions to control signal design as well as equipment selection are proposed.This dissertation focuses on development and validation of thesystem safety analysis tool for Gen-IV nuclear systems, mainly for SCWRand SFR, and its engineering application to safety analysis and safetysystem design improvement of the SCWR-FQT loop. The outcomings ofthis dissertation provide safety analysis tools and analysis results fordesign and licensing the SCWR-FQT loop, which give realistic referenceand guidance for the safty system design of the test loop.更多还原