您的位置：首页 > 论文页面
钠冷行波堆直流式蒸汽发生器瞬态特性研究
发表时间：2014-11-30 浏览量：2289 下载量：796
| 全部作者： | 韦宏洋，张大林，黄思洋，田文喜，苏光辉，秋穗正 |
| 作者单位： | 西安交通大学核科学与技术学院 |
| 摘 要： | 对直流蒸汽发生器（once through steam generator, OTSG）采用固定节点法进行数学建模，并研究其在稳定工况运行下的特性。与钠冷行波堆系统安全分析程序耦合，分析OTSG在反应性引入事故和失流事故下的瞬态特性。结果表明：发生失流事故后，堆芯传热恶化，为对反应堆实施保护，需紧急停堆。发生反应性引入事故后，堆芯功率上升会导致堆芯内燃料棒过热，可能会导致包壳破损，也会对反应堆的安全造成威胁。 |
| 关 键 词： | 核动力工程技术；行波堆；直流蒸汽发生器；反应性引入；失流事故 |
| Title： | Transient analysis for once through steam generator of sodium cooled traveling wave reactor |
| Author： | WEI Hongyang, ZHANG Dalin, HUANG Siyang, TIAN Wenxi, SU Guanghui, QIU Suizheng |
| Organization： | School of Nuclear Science and Technology, Xi’an Jiaotong University |
| Abstract： | In this paper, the fixed model method was used to simulate the once through steam generator (OTSG), and its character of steady state was researched. The transient performance of the OTSG under loss-of-flow accident and reactivity insertion accident were analyzed. The results showed that the reactor should be shut down due to the heat transfer deterioration in the core during the loss-of-flow accident. During the reactivity-insertion accident, the increasing core power will result in overheating in fuel rods, which might lead to fuel clad failure and threat the safety of the reactor. |
| Key words： | nuclear power engineering and techndogy; traveling wave reactor; once through steam generator; reactivity insertion; loss-of-flow |
| 发表期数： | 2014年11月第22期 |
| 引用格式： | 韦宏洋，张大林，黄思洋，等. 钠冷行波堆直流式蒸汽发生器瞬态特性研究[J]. 中国科技论文在线精品论文，2014，7（22）：2298-2306. |
0
评论数 0请您登录
暂无评论
下载全文
多维论文