系统安全分析程序在超临界水冷堆和钠冷快堆上的适用性研发与应用

发布时间：2018-09-12 07:14

【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。
[Abstract]:System safety analysis program (hereinafter referred to as system program) is an important tool for transient and accident safety analysis of reactor system. Under the background of the fourth generation advanced nuclear energy system research and development in the last decade, the international nuclear energy community has carried out a lot of research work on the fourth generation reactor system program. Due to the mature development of the LWR system, some of them have been modified to be suitable for the fourth generation nuclear power system after comprehensive system verification and extensive application. The applicability and reliability of these modified procedures need further study. In this paper, the model development, verification and application of system program for supercritical water cooled reactor and sodium cooled fast reactor in the fourth generation reactor are carried out. Firstly, the applicability of ATHLET program for light water reactor system on these two fourth generation reactor types is evaluated. Based on this, the secondary model of ATHLET program is developed, that is, the relevant calculation model suitable for supercritical water and sodium fluids is developed. The multifluid system program ATHLET-MF (Multi-Fluid) is obtained. Secondly, the modified ATHLET-MF program is preliminarily verified, and the natural convection experiment of France PHENIX sodium cold fast reactor is used to evaluate the program. Finally, The ATHLET-MF program is applied to the safety analysis of the experimental circuit for fuel performance verification of supercritical water-cooled reactor, and some suggestions for improving the design of the safety system of the experimental loop are presented. The main work of the thesis includes: 1. The applicability evaluation and multi-fluid model development of ATHLET program: (1) analyzing the applicability of ATHLET program to supercritical water cooled reactor and sodium cooled fast reactor; (2) increasing physical property calculation, heat transfer, pressure drop and critical flow model of supercritical water; (3) increase the physical properties of sodium, heat transfer, pressure drop model; (4) introduce multi-fluid universal interface, expand the program for supercritical water and sodium into multi-fluid model, obtain the version of ATHLET-MF program. 2. The preliminary verification and evaluation of the multi-fluid model of ATHLET-MF program: (1) the preliminary verification of the expansion function of supercritical water cooled reactor, including the comparison with the theoretical calculation and the program verification; (2) the evaluation of the expansion function of the sodium cooled fast reactor, That is, PHENIX reactor natural convection experimental verification. The results show that: ATHLET-MF program has good applicability and reliability for transient simulation of supercritical water cooled reactor and sodium cooled fast reactor system. The application of the multi-fluid model of ATHLET-MF program, that is, the safety analysis of the experimental circuit for fuel performance verification of supercritical water-cooled reactor: (1) five kinds of design benchmark accidents are calculated and analyzed, including coolant loss, main pump clamp shaft, test circuit power outage. The coolant channel blockage and the coolant side flow accident caused by the rupture of the internal components of the pressure pipe; (2) the improvement measures for the defects of the design of the initial safety system are put forward: two additional safety signals are added, A long-term waste heat discharge scheme is proposed and feasibility analysis is carried out. (3) sensitivity analysis of some design parameters of the safety system is carried out and some suggestions on the control signals and equipment parameters of the safety system are put forward. The purpose of this paper is to develop and verify the system safety analysis tools suitable for supercritical water cooled reactor and sodium cooled fast reactor. The purpose of this paper is to carry out safety analysis for the fuel performance verification experimental loop of supercritical water cooled reactor, and to explore the dynamic and safety characteristics of supercritical water cooling system. The improvement direction of safety system design is put forward. This paper provides a safety analysis tool and analysis results for the design of the experimental loop for fuel performance verification and the application for a safety license for the supercritical water cooled reactor. It is of practical significance for the design of the safety system of the experimental circuit.
【学位授予单位】：上海交通大学
【学位级别】：博士
【学位授予年份】：2013
【分类号】：TL364.1

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