首页 | 本学科首页   官方微博 | 高级检索  
     检索      

基于两区模型的钠冷快堆无保护失流事故
引用本文:郭超,陆道纲,刘卢果,何航行,徐良剑,沈才芬.基于两区模型的钠冷快堆无保护失流事故[J].科学技术与工程,2019,19(6).
作者姓名:郭超  陆道纲  刘卢果  何航行  徐良剑  沈才芬
作者单位:中国核动力研究设计院,成都610213;中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213;华北电力大学核科学与工程学院,北京102206;华北电力大学非能动核能安全技术北京重点实验室,北京102206
摘    要:为了研究钠冷快堆的固有安全性,研究了适用于钠冷快堆系统分析的理论模型,根据钠冷快堆的特点开发了SAC程序。针对钠池温度计算不准确问题,提出了两区模型。利用三维模型计算钠池主流区,采用提出的两区模型计算钠池温度的瞬态响应。选取了美国实验增殖反应堆(EBR-II)的无保护失流事故实验进行计算对比分析,采用三维钠池模型对钠池流场进行计算和分析,采用两区模型有效地计算了钠池温度瞬态响应。程序计算的事故瞬态结果与实验结果符合较好,验证了SAC程序进行快堆瞬态计算的准确性,同时证明了利用金属燃料的钠冷快堆的固有安全性。

关 键 词:钠冷快堆  安全分析  失流事故  固有安全性
收稿时间:2018/10/12 0:00:00
修稿时间:2019/2/25 0:00:00

Sodium-cooled Fast Reactor Loss of Primary Flow Without Scram Accident Analysis by Using two-zone model
GUO Chao,Lu Dao-gang,LIU Lu-guo,HE Hang-xing,XU Liang-jian and SHEN Cai-fen.Sodium-cooled Fast Reactor Loss of Primary Flow Without Scram Accident Analysis by Using two-zone model[J].Science Technology and Engineering,2019,19(6).
Authors:GUO Chao  Lu Dao-gang  LIU Lu-guo  HE Hang-xing  XU Liang-jian and SHEN Cai-fen
Institution:Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy, North China Electric Power University,Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China,Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China,Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China,Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China
Abstract:In order to research the inherent safety of SFR, the model suitable for SFR was researched and SAC code was developed according to the characteristics of SFR. In order to solve the problem of inaccurate temperature calculation of sodium pool, a two-zone model was proposed. Three-dimensional model is used to calculate flow pattern in the sodium pool and two zone model is used to calculated sodium temperature. The Loss of Flow Without Scram accident experiment of EBR-II is selected to validate the code. The three-dimensional sodium pool model is used to calculate and analyze flow pattern in the sodium pool and two-zone model accurately simulates the main flow phenomenon. The results calculated by the code have a good agreement with experiment and the code is validated to be effective for safety analysis of SFR. The inherent safety of SFR which adopts metal fuel is validated.
Keywords:SFR  Safety Analysis  LOF    Inherent  Safety
本文献已被 万方数据 等数据库收录!
点击此处可从《科学技术与工程》浏览原始摘要信息
点击此处可从《科学技术与工程》下载免费的PDF全文
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号