摇摆条件下海上浮动堆全厂断电事故分析

发布时间：2018-03-17 04:27

本文选题：海上浮动堆　切入点：非能动余热排出系统　出处：《原子能科学技术》2017年11期 　论文类型：期刊论文

【摘要】：为研究海洋条件对海上浮动堆全厂断电事故后的事故进程及非能动安全系统运行特性的影响,通过建立海洋条件加速度场模型,基于RELAP5程序开发获得了适用于海上浮动堆的系统分析程序,并对程序进行了实验验证。利用所开发的程序通过建立双环路海上浮动堆及二次侧非能动余热排出系统的计算模型,开展了不同摇摆运动参数下海上浮动堆全厂断电事故的计算分析。计算结果表明,船体的横摇运动可加快全厂断电事故后浮动堆系统压力和温度的下降速度,堆芯余热能够被二次侧非能动余热排出系统有效导出;但横摇运动会造成事故后堆芯自然循环流量的显著降低,引起一回路系统和非能动余热排出系统中自然循环流量的大幅度振荡及周期性倒流。本文计算结果可为海上浮动堆非能动安全系统的设计提供参考。
[Abstract]:In order to study the influence of ocean conditions on the accident process and the operating characteristics of inactive safety system after the power failure of the whole plant of floating reactor at sea, the acceleration field model of marine conditions is established. A system analysis program for floating reactor at sea is developed based on RELAP5 program, and the program is verified by experiments. The calculation model of double loop floating reactor and secondary inactive residual heat discharge system is established by using the developed program. The calculation and analysis of the power failure accident of the whole plant of the floating reactor at sea under different swing motion parameters are carried out. The calculation results show that the rolling motion of the hull can speed up the pressure and temperature drop of the floating reactor system after the power failure accident in the whole plant. The residual heat of the core can be effectively derived by the secondary passive residual heat removal system, but the natural circulation flow rate of the reactor core decreases significantly after the accident caused by the rolling motion. It causes large amplitude oscillation and periodic backflow of natural circulation flow in primary circuit system and inactive residual heat discharge system. The results in this paper can provide reference for the design of inactive safety system of floating reactor at sea.
【作者单位】：哈尔滨工程大学核安全与仿真技术国防重点学科实验室;中广核研究院有限公司;
【基金】：黑龙江省青年学术骨干支持计划资助项目(1254G017) 中央高校基本科研业务费专项资金资助项目(HEUCFD1512,HEUCFD1513)
【分类号】：TL364.4

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