期刊文献+

LOCA下喷放参数对冷却剂喷放特性影响数值研究 被引量:2

Numerical Study on Influence of Blowdown Parameter on Coolant Blowdown Characteristic in LOCA
下载PDF
导出
摘要 冷却剂喷放过程是失水事故(LOCA)的重要过程之一,研究冷却剂喷放过程的热工水力特性对认识LOCA以及预测事故后放射性源项迁移过程有着重要意义。本文利用FLUNET软件建立冷却剂喷放数值计算模型,并对其进行验证。利用模型研究喷口直径、喷放距离和喷放压力等喷放参数对计算域内流场温度、液滴速度和蒸汽流速等特性的影响。研究结果表明:喷口直径的提高使得喷放参数均有提高;随喷放距离的增大,流场温度和液滴速度先上升后下降,而蒸汽流速先上升后趋于平稳;喷放压力越大,喷放参数的最大值离喷放出口越远,液滴速度和蒸汽流速的最大值随喷放压力的增大逐渐上升,而流场温度最大值没有变化。 The coolant blowdown process is one of the important processes of the loss of coolant accident(LOCA).It is of great significance to study the thermal hydraulic characteristics of coolant blowdown process for understanding LOCA and predicting the migration process of radioactive source term after accident.The numerical simulation model of coolant blowdown was established by FLUENT software and verified.The model was used to study the effects of blowdown parameters such as diameter of nozzle,blowdown distance and blowdown pressure on flow field temperature,droplet velocity and vapor velocity.The results show that the increase of diameter of nozzle increases the blowdown parameters.As the blowdown distance increases,the flow field temperature and the droplet velocity increase first and then decrease,while the vapor velocity first rises and then stabilizes.The greater the blowdown pressure is,the farther the blowdown parameter is from the blowdown outlet.The maximum values of droplet velocity and vapor velocity increase gradually with the blowdown pressure,while the maximum value of the flow field temperature does not change.
作者 柯炳正 高璞珍 王博 陈博文 温济铭 田瑞峰 KE Bingzheng;GAO Puzhen;WANG Bo;CHEN Bowen;WEN Jiming;TIAN Ruifeng(Fundamental Science on Nuclear Safety and Simulation Technology Laboratory,Harbin Engineering University,Harbin 150001,China)
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2020年第10期1858-1865,共8页 Atomic Energy Science and Technology
关键词 失水事故 冷却剂喷放 闪蒸 临界流动 数值计算 loss of coolant accident coolant blowdown flashing critical flow numerical calculation
  • 相关文献

参考文献8

二级参考文献46

  • 1季松涛,张应超.用ICARE2程序模拟秦山核电厂熔渣床的形成[J].原子能科学技术,2004,38(z1):16-18. 被引量:1
  • 2孙显锋,孙学文,赵锁奇,徐春明.超临界溶剂脱沥青操作参数对辽河稠油减压渣油脱油沥青的影响[J].石油炼制与化工,2010,41(2):30-34. 被引量:4
  • 3骆邦其.冷热段同时安注时的大破口失水事故分析[J].核动力工程,1996,17(5):391-394. 被引量:2
  • 4国家核安全局.HAF102,核动力厂设计安全规定[S].北京:周家核安全局,2004.
  • 5U.S. Nuclear Regulatory Commmsion Regulations. 10CFR50. Code of Federal Regulations [S]. U. S. NRC, 2006.
  • 6US Nuclear Regulatory Commissions, RG 1. 157, BestEstimate Calculations of Emergency Core Cooling System Performance[S]. U.S. NRC, May 1989.
  • 7Westinghouse LLC, Westinghouse AP1000 Design Control Document[ R]. Westinghouse Electirc Company LLC, 2008.
  • 8U.S. NRC. Final Safety Evaluation Report: Related to certification of the AP1000 standard design[R]. U.S. NRC, 2004.
  • 9T Wicket, et al. Report of the Uncertainty Methods Study for Advanced Best Estimate Thermal Hydraulic Code Applications[M]. 2 vols, Rep. NEA/CSNI R(97) 35. Paris: OECD, 1998.
  • 10Reyes J N, Hochreiter Jr L. Scaling Analysis for the OSU AP600 Test Facility (APEX) [J]. Nuclear Engineering and Design, 1998, (186): 53-109.

共引文献53

同被引文献30

引证文献2

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