期刊文献+

日本文殊快堆紧急停堆后堆芯出口腔室瞬态工况模拟研究 被引量:1

Numerical Analysis of Transient State in Reactor Upper Plenum of Monju Fast Reactor after Trip
下载PDF
导出
摘要 基于日本文殊快堆停堆实验数据,完成了文殊快堆上升桶通流孔结构分别为直角、圆角下堆芯出口腔室内较完整的热分层进程模拟,并从热分层的形成、界面上升速度、温度梯度及通流孔钠流量比率等方面对热分层特点进行深入分析。结果表明,数值模拟结果与实验结果符合较好,在一定条件下,数值模拟可很好地预测钠冷快堆内整体热工水力行为。本文结果为建立一套用于预测钠堆内复杂瞬态工况的数值模拟方法积累了经验。 Based on the turbine trip test results of Monju fast reactor,the whole development process of thermal stratification after the turbine trip in upper plenum,using holes with sharp and round edge on the inner barrel,was simulated.The stratification characteristics including thermal stratification forming,interface rising speed,temperature gradient and flow ratio of flow hole to the annulus gap were investigated.The results show that the numerical simulations agree well with the experimental results and the thermal-hydraulic phenomenon in fast reactor can be preferably forecasted by numerical simulation under some conditions.The experience of building a numerical simulation method to forecast complicated transient state case is accumulated.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2017年第10期1827-1833,共7页 Atomic Energy Science and Technology
关键词 文殊快堆 出口腔室 停堆实验 热分层 数值模拟 Monju fast reactor upper plenum trip test thermal stratification numerical simulation
  • 相关文献

参考文献1

二级参考文献6

  • 1YOSHIKAWA S, MINAMI M. Data description for coordinated research project on benchmark analyses of sodium natural convection in the upper plenum of the Monju reactor vessel under supervisory of technical working group on fastreactors[R]. Vienna: IAEA, 2008.
  • 2SHIBAHARA M, TAKATA O, YAMAGUCHI A. Numerical analysis of thermal stratification in the reactor upper plenum of Monju with 1/3 sec- tor and full sector models[C]//The 14th Interna- tional Topical Meeting on Nuclear Reactor Ther- mal Hydraulics. Canada.. Es. n. 1, 2011.
  • 3OHIRA H. Steady state results and key informa- tion for the calculations[C]//4th RCM of the IAEA CRP on Benchmark Analyses of Sodium Natural Convection in the Upper Plenum of the Monju Reactor Vessel. Japan: Is. n. 1, 2012.
  • 4BIEDER U, FAUCHET G, YOSHIKAWA S. TRIO_ U analysis of natural convection in the upper plenum of the Monju reactor [C] // 4th RCM of the IAEA CRP on Benchmark Analyses of Sodium Natural Convection in the Upper Ple- num of the Monju Reactor Vessel. Japan: [-s. n. 1, 2012.
  • 5SOFU T, THOMAS J W. Analysis of thermal stratification in the upper plenum of the Monju reactor vessel[C]//4th RCM of the IAEA CRP on Benchmark Analyses of Sodium Natural Con- vection in the Upper Plenum of the Monju Reac- tor Vessel. Japan: Is. n. ], 2012.
  • 6SHVETSOV Y. Analysis of transient sodium flow and temperature distributions in the upper plenum of Monju reactor[C]///4th RCM of the IAEA CRP on Benchmark Analyses of Sodium Natural Convection in the Upper Plenum of the Moniu Reactor Vessel. Japan: s. n. 1, 2012.

共引文献2

同被引文献2

引证文献1

二级引证文献1

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部